Text

Rev 6 to Crisis Mgt Plan Implementing Procedure EDA-2, Offsite Dose Projections for Catawba Nuclear Station
	ML20072T695
Person / Time
Site:	Catawba
Issue date:	04/04/1991
From:	Harris R; DUKE POWER CO.
To:	;
Shared Package
ML15224A891	List: ML20072T695;
References
	EDA-2, NUDOCS 9104180228
	Download: ML20072T695 (27)
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l CRISIS MANAGEMENT PLAN I

IMPLEMENTING PROCEDURE EDA - 2 "Off-Site Dose Projections for Catawba Nuclear Station" O

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Approved By Date 4

O V Rev. 6 April 1, 1991 9104180228 910408 3 DR ADOCK 0500

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

' EDA-2

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"' Page lof 11 DUKE POWER COMPANY.

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0FF-SITE DOSE PROJECTIONS FUR CATAWBA NUCLEAR STATION

!1.0 PURPOSE To describe a method for projecting dose commitment from a noble gas and/or lodine release, through the containment, the unit vent and/or the steam relief valves, during an emergency.

2.0. REFERENCES' 2.1 HP/0/B/1000/10 Determination of Radiation Monitc,r Setpoints 2.2~ HP/0/B/1009/06, Alternative Nethod for Determining Dose Rate Within the Reactor Building 2.3 HP/0/B/1009/14, Radiation Protection Actions Following an Uncontrolled Release'of Liquid Radioactive Material

-2.4 HP/0/B/1009/17, Unit 1 Post-Accident Containment Air Sampling- System 2.5- HP/0/B/1009/21,_ Abnormal Unit Vent Sampling i

2.6 CNS Technical Specification 3.6.1.2 2.7- Offsite. Dose Calculation Manual (ODCM) .

O 2.8 Regulatory Guide 1.4, " Assumptions Used for Evaluating the

. T Potential Radiological Consequences of a Loss of Coolant Accident '

for: Pressurized Water Reactors"

-2.9- Regulatory Guide 1.109, " Calculations of Annual Doses to Man from

= Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR Part 50,: Appendix I"

' 2.10 - NuReg-0396, EPA 520/1-78-016, '" Planning Basis for the Development of

- State and Local Government Radiological Esmrgency Response Plans in Support.of Light Water: Nuclear Power Plants" 2.11- NuReg-0654, FEMA-REP-1, Rev.II,;" Criteria for Preparation and Evaluation .of Radiological: Emergency Response Plans and Preparedness

-in- Support:of Nuclear. Power Plants" 2.12. Letter from F. G. Hudson, September 30, 1985, re: Release Rate Information. for:McGuire and Catawba Nuclear Station (File: CN-134.10) 2.13: Catawba' Nuclear Station Class A Computer Model Validation (Filei NUC-0306) l-p '2.14 Letter- from J. E. Thomas, May 19, L 1987, File: CN-1346.05 and

, personal-conversation with Frank Poley 2.15 Radiolodine and Particle Transmission Through Plant Vent Sampling Lines at Catawba Nuclear Station, prepared by SAIC, dated July 1989.

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EUA-2 Page 2 of 11 2.16 Letter from C.D. Ingram, June 7, 1989, re: Guidance for Off-site Protective Actions Containment Design Leak Rate Validation. File O No.: CN-134.10 3.0 LIMITS AND PRECAUTIONS 3.1 This procedure is an alternative method of dose assessment to the Catawba Class A Atmospheric Dispersion Model computer code.

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

3.3 It is assumed that the whole body dose from an lodine 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 list of af fected zones, it shall not be removed except under the direction of the Dose Assessment Coordinator.

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

4.0 PROCEDURE 4.1 Hoteorology Assessment 4.1.1 Acquire the following information and record on the Dose Assessment Worksheet (Enclosure 5.1):

4.1.1.1 Lower 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 wLnd direction is not available.

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EDA-2 Page 3 of 11 4.1.1.2.2 If the wind speed or wind direction cannot be obtained from plant O systems, obtain them from the National Weather Service (phone 704-359 8466). If the NWS information is unavailable, then obtain data from McGuire Nuclear Station Control Room (73 or 78, then 875, then ext. 4262, or 4263, or 4264).

4.1.1.3 Temperature gradient ( AT) in degrees centigrade.

4.1.1.4 Using Enclosure 5.2, record the stability class based on 6T.

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 meteorological data for calculating doses due to changing meteorological 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 H

) fr m ne sure 5.2.

4.1.2.2 Convert the Cg values to X/Q:

X/Q = C g WS 4.2 Source Term Assessment - Steam Relief Valve (Enclosure 5.4) 4.2.1 Determine the Sub-Noble Gas Release Rates, SQgg (C1/sec),

by the following method:

O

EDA-2 Fage 4 of 11

,s 4.2.1.1 For Unit 1-EMF 26, EMF 27, EMF 28 and EMP29 or for Unit 2-EMF 10, EMF 11, EMF 12, EMF 13:

SQ NG = R/hr x 1 x LBM x CF Ci V0 PEN lbm R/hr D where:

R/hr = EMF 26, EMF 27 EMF 28 EMF 29, EMF 10, EMF 11. EMF 12 EMF 13 reading V0 PEN = time the valve is open in seconds LBM = lbm released for the time the valve was open CF = correction factor per Enclosure 5.5 4.2.2 Determine the Noble Gas Release Rate, QNG(C1/sec):

Q NG

80 )+

SQ'NG((

NG MF29) MF26) + SQNG( MF27) + SQNG( "

4.2.3 Determine the Iodine release rate, Q (Ci/sec):

7 Qy =QNG

where:

Irat = ratio of 1131 eqv./Xe133 eqv. from Enclosure 5.6.

4.2.4 Record Q NG and Q7 on Enclosure 5.1, page 2, 4.3 Source Terin Assessment - Containment (Enclosure 5.7) 4.3.1 Determine the Noble Gas Release Rate, QNG(C1/sec) based on ,

one of the following methods:

4.3.1.1 Based on an EMF reading, where; Q pg = EMF x CF x W where; EMF = 39(L), if EMF 39(L) <1E7 cpm and flowpath not isolated, EMF = 39(H), if EMF 39(L) is offscale and EMF 39(H) > 100 cpm and flowpath not isolated, EMF = 53A or 53B, if EMF 39(H) is offscale.

Use survey meter reading (Reference 2.2) if 53A and 53B are not available.

CF = correction factor per Enclosure 5.8.

O

. EDA-2 Page 5 of 11 LR = Leak Rate x BYPASS, Leak Rate, (ml/hr), by one O of the following methods:

] based on containment pressure:

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

LR = OIC (from Enclosure 5.10) based on design leak rate:

LR = 4.18E6 (Reference 2.16)

BYPASS = Bypass leakage, default is 77.

or 0.07 (Reference 2.6) 4.3.1.2 Based on PACS sample, where; Q NG ^ *

where; PACS = pCi/ml (Reference 2.4)

CF = 2.78E-10 Ci hr see pCi LR = Leak rate, as determined in Step 4.3.1.1 above 4.3.2 Detemine the Iodine Release Rate, Q7 (Ci/sec) based on one of the following methods:

4.3.2.1 Based on Q NG I Q

7

=Q gg x Irat where:

Q gg = Noble Gas Release Rate as determined in Step 4.3.1 above Irat = ratio of 1131 eqv./Xe 133 eqv. from Enclosure 5.6.

4.3.2.2 Based on EMF 40 (if flowpath is not isolated);

Qy = 6 CPM x 9.82E-20 Ci hr min x LR Amin see ml cpm O

EDA-2

- Page 6 of 11

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where:

ACPM = reading from EMF 40 Delta Counts 6 min = the time interval for EMF 40 observation (normally 15 minutes) 9.82E-20 = 4.0E-5 pCi/ cpm x .25 min /ft' (inverse of EMF flow rate) x 3.53-5 ft*/ml x 1Ci/1E6 pC1 x 1 hr/3600 sec.

4.0E-5 = correlation factor for EHF40 from Reference 2.1.

LR = Leak rate, as determined in Step 4.3.1.1 above 4.3.2.3 Based on PACS sample; Q3 = PACS x CF x LR where; PACS = (pC1/ml) (Reference 2.4)

CF = 2.78E-10 Ci hr sec pCi LR = Leak rate as determined in Step 4.3.1.1 above 4.3.3 Record Q NG and Qy on Enclosure 5.1, page 2.

4.4 Source Term Assessment - Unit Vent (Enclosure 5.11) 4.4.1 Determine the Noble Gas Release Rate, QNG(Ci/sec) based on one of the following methods:

4.4.1.1 Based on as EMF reading, where; Q gg = EMF x CF x CFM where:

EMF = 36(L) if EHF36(L) < IE7 cpm, EHF = 36(11) if EMF 36(L) is offscale and EMF 36(II) > 100 cpm and compressor not tripped, EMF = 54 if EHF36(H) is offscale or compressor tripped.

CF = correction factor per Enclosure 5.12 O CFM = unit vent flow rate (ft*/ min)

, EDA-2

,- Page 7 of 11 4.4.1.2 Based on unit vent sample, where;

() QNG " "' "" "*E " * * "

where:

Unit Vent Sample = (pCi/ml) per Reference 2.5 CF = 4.72E-4 Ci min mi sec ft* pei CFM = unit vent flow rate (ft*/ min) 4.4.2 Determine the Iodine Release Rato, Q3 (Ci/sec), based on one of the following methods:

4.4.2.1 Based on Q NG I Q

7

=Q NG " #"

where:

Q gg = Noble Gas Release Rate as determined in Step 4.4.1 above Irat = ratio of 1131 eqv./Xe133 eqv. from Enclosure 5.6, 4.4.2.2 Based on EMF 37 (if compressor not tripped);

ALEH x 1.33E-13 Ci min min x CFM = Q 7 Amin sec ft* cpm where:

ACPM = reading from EMF 37 Delta Counts Amin = the time interval from EMF 37 observation (normally 15 minutes) 1.33E-13 = 4.0E-5 pCi/ cpm x 0.1667 min /ft*

(inverse of EMF flow rate) x 1C1/1E6 pC1 x 1 min /60 sec x 1.2 where:

4.0E-5 = correlation factor for E!!F37 from Reference 2.1.

1.2 = inverse of iodine transmission factor (see Reference 2.15)

CFM = unit vent flow rate (ft /3 min)

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-EDA-2 4

Page 8 of 11- ;

4.4.2.3 Based on unit vent sample:

Q7 .= Unit vent sample x 4.72E-4 C1 min ml x CFM see ft* 901' ,

where:

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

CFM = unit vent flow rate (f t'/ min) 4.4,3- " ""

Record _QNG "" S 1 ""#* ' ' E*I *

.-4,5 Dose Assessment (Enclosure 5.1 or Class A computer printout)-

4.5.1 _On Item 1, record if this information is for a drill or real emergency.

4.5.2 On item 2, record which- unit is af fected.

4.5.3 On Item 9, record the reactor status.

4.5.3.1 If the reactor has not trirn-d, use the data sheet date/ time as the tiu.6 er reactor trip.

]

l On the computer printout, sr m out the i shutdown time /date-and record the % Power from the data -sheet.-

, - k

-Q 2' On Item _101: determine release status by the following

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4.5.4 guidance' criteria:- 1 4.5.4.1 .No Release .no: potential release of acttvity

-generated by . the event.

4.5.4.2 Potential Release - activity generated by the;

-event that can potentially be released, but-is_ _

not currently being released.

4.5.4.3 Release Within Normal bopratinn Limits _-

activity generated by the event' currently or previously released within. normal operating limits:-(less'than_1.00dE-2. mrem /hr whole body or less than_1.711E-1 mrem /hr child thyroid). >

4'.5.4,4 Release Above' Normal Doerotinn Limits - activity.

- generated- by .the event--currently or previously -

released above normal operating 11mits (greater 1

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than or equal 1.008E-2 mrem /hr whole body or 4 greater than or equal 1.711E-1 mrem /hr child 1 thyroid).

_ 4.5.5 On- Item 11,: record what type of release has occurred.

10 4.5.6- On Item 12, record the noble gas and iodine release rates (curies per second) from all releases. )

1

- ,--~a ---- -- u- - - - - - - - " w e- -- n- + e w

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EDA 2 !

Page 9 of 11

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4.5.t '

If whole body dose rates exceed 1.008E 2 mrem /hr or thyroid dose rates exceed 1.711E*1 O

mrem /hr, check above normal operating limitsi l l' otherwise, check below. l L 4.5.6.2 If available,, record the highest fodine/ xenon

ratio.

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

4.5.731 If new doses were calculated, check the NEW block.

4.5.7,2 The duration is the total time of previous 1 releases plus the time estimated for the l projected release._

4'5.7.3

. The integrated dose (mrem) is the total dose from all releases plus the dose from the l projected release, j

- 4.5.7.4 If information is available contradicting the calculated doses, change the data to reflect

, the new values..

4.5.7.5 On Enclosure 5.1: i

}

4.5.7.5.1 Determine the Projected Whole Body Dose Rate, DRwb (rem /hr), due to .

the' noble gases for .5, 2, 5 end 10 miles: ,

~

8 DRwb-= 33.6 ren m x TQNG * /0 hr Ci where 33.6 is the adult whole body-dose conversion factor from Reference 2.9 in' rem n 8 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 milesi <

Dwb = DRwb x 2 hr whores.

dose is integrated over 2. hour time period-4 4 ,m . , m.,-.m.._.. ._ _ _ .- _ ____ _ _ _ ________ ___ _ __ u

4

. EDA-2 Page 10 of 11 4.5.7.5.3 Determine the Projected Thyroid Dose Rate, DRet (rem /hr), due to O. iodine for .5, 2, 5 and 10 miles:

d-DRet

X/Q x TQg x 2.26E6 rem m' 7 hr C1 where:

2.26E6 is the child thyroid dose conversion factor from Reference 2.13 in rem _ml hr Ci 4.5.7.5.4 Determine the Projected Thyroid Dose, Det(rem), due to iodine for

.5, 2, 5 and 10 miles:

F Det = DRet 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 4.5.8 List any whole body or child thyroid dose rate less than

.0001 mrem /hr as "less than background" (where'.0001 is an-O. assumed value based on yearly ef fluent data).

4.5.9 On Item 14, record the meteorological data.

4.5.10 On Item 16, this section is for-the TSC Dose Assessment Coordinator or the CMC off Site Dose Assessment Director.

- 4.6 Protective Action Recommendations (Enclosure 5.1 or Class A '

computer printout): .

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

based upon 1) the wind speed and-wind direction, using Enclosure 5.3; and 2) the projected dose from Enclosure 5.1 compared to the following, r 4.6.2' If_the projected dose in a PAZ_is < 1 rem whole body or

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

4.6.3 If.the projected dose in a PAZ is 1 - 5 rem whole ' body or L5 - 25 rem thyroid, then recommend to consider evacuating

- pregnant women and children and shelter all other PAZs-

(actions OTHER and.B).

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

> 25 rem thyroid, then recommeni svacuate everyone=and shelter'all other PAZs (actions C and B). ,

_.ze.upe.,4.,.--m.- -u ,.%,.- ...- mu_.y.-.w.w-re,. - ,---.,.,$,.-m._m___-,___m_.. _ _ _ _ _ _ . _ _ - _

- __-_.___---__v,---..--e-

EDA-2 Page 11 of 11 4.6.5 Recheck meteorology conditions approximately every 15 minutes to ensure that other sectors have not been O affected.

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

4.7.2 If the dose rate at the site boundary is 15.00-4 rem /hr whole body then recommend an Alert.

4.7.3 If the dose rate at the site boundary is t .05 rem /hr whole body or 2 25 rem /hr thyroid, then recommend a Site Area Emergency.

4.7.4 If the dose rate at the site boundary is 21 rem /hr whole body or 2 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 (Cg )

5.3 Protective Action Zones Determination 5.4 Sample of Source Term Assessment - Steam Relief Valves 5.5 EMF 26, EMP27, EMF 28, EHF29 or EMF 10, EHFil, EHF12 EMF 13 Noble Gas Correction Factor 5.0 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 O

EMERGENCY NOTIFICATION ["$8"$j'A

1. @ T t$ t$ A DRILt @ ACTilAL(McRGENCY OlNITIAL Orottow.UP- Mr$$AGt NUMetR

!. 'SITt: UNIT: REP 0FlitD BY:

. TRANSMITTAL TIMt/DATE: gl7 / CONFiRMAil0N PHONE NUMBER:

4. AUTHr.NTICATION (11 Required):

AmDer) (coornere)

6. EMERGENCY CLA$$1FICAtl0N:

@ NOTIFICATION OF UNUSUAL IVINT @ At[RT @ Slit AREAtM!RGENCY @ GENERAllMERGENCY I

6. @ imergency Declaration At: @ Termination At: TIMt/DATE:

(145terri) mm

/. CC

.l. yy (If E. co to ltem 16.)

l I

7, EMER0tNCY Ot$CRIPTION/ REMARK $:

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8. PLANT CONDITION: @ IMPROVWG @ STABLE @ O! GRADING

9. REACTOR STATUS: @ SHUTDOWN: TIMt/ Daft:

(Isstern; mm

/

co

/. yy

@ % POWER

10. tMERGENCY REllA$t($):

@ NONt (Go toitem 14 ) @ POTENTIAL (Go to item id<)@ IS OCCURRING @ HAS OCCURRtD "11, TYPt 0F RtLEA$t: 0 ttiv5Tt0 0 GR0uNottvtt

@ AIRBORNE: Started: _ / / ' Stopped. / /

im (tastern) Date Time (tastem) Dre

)

O

.L

@ tt0VID. Started.

Tre (Iastem)

/

Date

/ Storped:

Time (Iastem)

/

Oxe

/- )

J 1

"12. AtLEAst MAGNITUDE: O CuRitS Pta StC. O cuRitS NORMAt OPinATiNo tiMrTs: O BeLOW D AB0ve

@ NOBLt GASES - @ IODINES

@ 100lNt/NOBLt GAS RATIO (if swailable) @ OTHER "13. ESTIMAit 0F PROJECT!D OFF$ lit DO$t: O New 0 uNCHANGto eSTiMAfto ounATioN HRS Wholebefy Child Thyroid Wholobody Child Thyroid DOSI RATI 00st Mr! 00$t 00$t (mremk) (mrem lht) (mrom) (mrem)

SITt BOUNDARY - _

2 MILtS S MILES -

10 MILES .

@ SPet0(mph)

"14. METEOROLOGICAL MTA: @ WINDOIRECTION(from) ,

@ STABILITYCLASS @ PRECIPITATION (type) 15, RtCOMMENDED PROTICTNE ACTIONS:

@ NORtCOMMENDEDPROTECTNr ACTIONS

@ EVACUATt l @ SHtLTERIN PLRt t @ 0THtR

16. APPROVtD BY; TIME /DATE:

_/ /

It items 814 have not thanged, only llers 17 and 1516 are required to be templeted. ;

"Information may not be available on initial notifiestions, j km M866 (R7 90) -

1

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

l EDA . j ENCLOSURE 5.1 Page 2 of 2

' HETEOROLOGY, SOURCE TERM AND DOSE ASSESSHENT 1 3

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.......................................=..........=...........................

HQ,III: 1) For all evacuations, recommend that the remainder of the 10 mile emergency planning zone stay irdoors.

2) Compare these recommendations with other groups' recommendations that the Emergency' Coordinator / Recovery Manager reviews. y 1

-Projection based on data on / / Time since trip hrs.

i

\

. Hiles .$- 1 2 4 5 7 8 '

PAZ A0 B1 El Al C1 D1 T1 D2 A2 C2 D2 E2 T2 T3 A3 :

'l Total Source Tern Assessment a Current o Hypothetical Steam Relief Containment Unit Vent Encl. $ 4 Encl. 5.7 Encl. 5.11 >

C1/sec ** Ci/sec + Ci/Sec . 01/Sec (TQgg) 01/sec 4 C1/see + Ci/ Soc = C1/Sec (TQg )

Source Term Based on

1. LOCA . 5. Tube Rupture l

2. LOCA (charcoal) 6.. New Tuel Accident (< 100 hrs old) i

.3. Helted Core 7. Old Tuel Accident (> 100 hrs old) 4.- Helted Core (charcoal) 8. Waste Gas Decay Tank' C

-Dose Assessment ,,11 = X/Q AT =

WS

.< - <- Adult whole body < -< -> > Child thyroid- > --->

2 hr 2 hr

-Dose a 2 x DRwb = 33.6 x TQ x X x TQ x 2.26E6 = DRct x 2 Dose -

(rem)" (rem /hr) (Chsec)(se/Q c/mS ) (di/sec) (rem /hr) (rea)

Distance miles I

=2 x ' = 33.6 x TQ NG .5 % x 2.26E6 = x2 t

2 x = 33.6 x TQ NG 2 M x 2.26E6 = x 2a 2x = 33.6 x TQ gg -- 5 : - TQ .x 2.26E6:= -x 2

2x = 33.~6-x TQ NG 10- M .'x 2.26E6 = x 2.-

a2 x = 3.3.6 x TQ NG 1 M x 2. 6E6 = x 2r

2 x _ = 33.6 x TQ NG 4 % x 2.26E6 = x 2= i 2 x ,_ 'M x 2.26E6

31.6 x TQ NG 7 x 2

2, ,= 33.6 x:TQgg 8 M x 2.26E6 = x 2=

-Review with Emergency. Coordinator the recommended Emergency Classification.

o:-Recommend Alert Jol Recommend Site Area Emergency

"*"""""""*"""~""'

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i DUKE POWER COMPANY ,

. CATAWBA NUCLEAR STATION l EDA-2

/^\ ENCLOSURE 5.3 V PROTECTIVE ACTION ZONES DETERMINATION Determine the affected zones (based on wind direction) from the table below and record-on Enclosure 5.1.

@lE: If wind speed is less than or equal to 5 mph, the af fected zones for 0-5 miles shall be A0, A1, B1, C1, D1, El, F1.

Wind Direction PAZ's (degrees from North) 0 5 miles 5 10 miles 0.0 - 22 A0, C1, D1 C2, D2 22,1 - 75 AO , C1, D1, El C2, D2, E2, F2 73.1 - 108 AO,C1,D1,E1,F1 D2, E2, F2, F3 108,1

120 A0, D1, E1, F1 D2, E2, F2, F3 120.1 - 159 A0, El, F1 D2, E2, F2, F3, A2 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 AO,A1,B1,C1 A2, B2, A3, C2 298.1 - 338 A0, B1, C1 B2, A3, C2, D2 338.1 - 359.9 A0, B1, C1, D1 B2, C2, D2 I -

(j,

DUKE POWER COMPANY

' CATAWBA NUCLEAR STATION EDA-2 ENCLOSURE 5.4 O SOURCE TERM ASSESSMENT - STEAM RELIEF VALVES Report #

Reactor Trip / Projection based on data on /

(Date/ Time) (Date/ Time)

Calculations based on Molted Core . .LOCA NOBLE GAS based on EMF 26 or EMF 10 SG NG R/hr x f 1 l l sec lx lbm x Q= A I l lbm R/hr sec (Encl. 5.5) based on EMP27 or EMF 11 R/hr x ! 1 l l sec lx lbm x M= A I I lbm R/hr see (Encl. 5.5) based on EMF 28 or EMF 12

. R/hr x l 1 l l sec lx lbm x .U= A I I lbm R/hr see (Encl. 5.5) based on EMF 29 or EMF 13 R/hr x l 1 l l sec lx lbm x G= A I I Ibm R/hr sec (Encl. 5.5)

Total from all Steam Relief Valves, QNG " UII8'"

IODINE Trom all Steam Relief valves 01 Q gg x 1131 eqv./Xe 133 eqv. ratio = Ci/sec (Encl. 5.6)

O o Emergency a Drill Prepared by:

-._._.-.-_.m___,____,_A___

l DUKE POWER COMPANY a

CATAWDA NUCLEAR STATION EDA-2

(]

()

ENCLOSURE 5.5 EHF26 EMF 27, EMF 28 EMF 29 or

)

EMF 10 EMF 11. EMF 12. ENT13 NOBLE GAS CORRECTION FACTOR Time Since Trip (hrs) Correction Factor based on Molted Core or LOCA 20 3.622 22 3.971 24 4.041 28 4.029 224 3.332 248 2.647 2100 2.438 3250 2.438 2500 2.438 2720 2.438

units in _ Ci lbe R/hr

Enclosure 5.5 la the correlation f actor per Reference 2.13 x 8

2.83E4 mL x .41 11 x m8 ft' lbm 1E6 ml

.41 = specific gravity of steam per Reference 2.13.

4

. DUKE POWER COMPANY

- CATAWDA NUCLEAR STATION EDA-2 ENCLOSURE 5.6 O 1131 eqv./Xe133 eqv. RATIO Ratio based on Ratjo based on LOCA Helted Core Timo Since Trip (hrs) (Column 1) (Column 2) 20 2.74E-3 2.24E-3 22 3.42E 3 9.66E 3 24 3.82E 3 1.59E-2 28 4.340 3 2.85E-2 224 4.79E-3 7.52E-2 248 4.84E-3 1.11E-1 2100 5.06E-3 1.33E-1 2250 6.55E 3 1.80E-1 2500 1.02E 2 2.90E-1 1.44E-2 4,33E-1 2720

Enclosure 5.6 is from Reference 2.13.

EQIL: For unit vent releases in which Irat is utilized to determine I-131 equiv. concentration, apply the appropriate correction from the O table below:

1. LRCA, use column 1 (based on LOCA).

2. LOCA throuch charcoal filteta, divide column 1 value by 100,

3. Core damare, use column 2 (based on Core Helt).

4. Core demane throuth charcoal filters, divide column 2 value by 100.

5. Tube rupture, use 1.44E-5

6. Nsw fuel accident, use 2.217E 4

7. Old fuel accident, use 7.217E-4

8. Gas _ decay tank, assume no radiolodine released, only noble gases are considered to be released from gas tank, use 0.

NQII: For gisan releases in which Irat is utilized to determine I-131 equiv. concentration, apply the appropriate correction from the table below:

1. LQgA divide column 1 value by 100.

2. Core damare, divide column 2 value by 100.

---_____m______ _

, DUKE POWER COMPANY

. . CATAWBA NUCLEAR STATION EDA-2

(

ENCLOSURE 5.7 SOURCE TERM ASSESSMENT - CONTAINMENT Report # _

Reactor Trip / Projection based on data on /

(Date/ Time) (Date/ Time)

Calculations based on _ Melted Core LOCA Containment pressure psig LR = ml/hr x BYPASS (default = .07) I LR tr. sed on __. Realistic Leak Rate (cheok one)-

1" 2" 4" 6" 8" 12" 18" 34" diameter opening (circle one) Personnel llatch opening Equipment flatch opening Design Leak Rate (4.1806)

NOBLE GAS based on (check one) o EHF39(L) if < 1E7 cpm o EMP39(ll) if > 100 cpm o EMT53 if 39(11) is off scale EMF CF LR Q NG cpm

'O

.d or x x ml/hr =

E (Encl. 5.8)

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

E sec pCi see 10 DINE based on O O NG I E x 1131 eqv./Xe133 eqv. = E sec ratio (Encl. 5.6) see based on EMF 40 LR ACPM x. 9.82E-20 Ci hr min x ml/hr =

E Amin see al epm see based on PACS sample di x 2.78E 10- Ci hr x ml/hr =

1 m1 sec pCi see o Emergency a Drill Prepared by:

,, / +

(

) EDA-2 ( )

DUEE POW CGMPANY

Enclosure 5.8 .

CATAWBA CONTAINMENT NOBLE GAS CORRECTION FACTOR -

Time Since EMF 39(L) EMF 39(H) EMF 53 Trip (hours) based on based on based on LOCA Melted Core LOCA Melted Core LOCA Melted Core 20 6.389E-IC 6.572E-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 23 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 5.58FE-14 2.335E-10 1.557E-10 2500 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 sec m1 cpm sec al R/hr Enclosure 5.8 is the correlation factor per Reference 2.13 x hr x C1 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 538 is less than or equal to .50 R/hr, add 150 R/hr to reading.

DUKE PO' DER COMPANY

- CATAWBA NUCLEAR STATION EDA-2 ENCLOSURE 5.9

.]

'v CONTAINHENT LEAKAGE RATE VERSUS PRESSURE file ml/.hr

-10 *2.081E5 12 4.536E5 14 8.316C5 18 1.397E6 l

210 1.$91E6 I

Ell 1.663E6 212 1.713E6 213 1.764E6 214 1.800E6 215 1.836E6 Enclosure 5.91s the realistic leakage rate (m'/sec) per Reference 2.12 x IE6 ml/m* x 3600 sec/hr.

2.081ES ml/hr-is derived as - follows:

A V 2.081E5 ml = 0.017 %/ day x 3.4E 3 m 8 -day x 106 al x-3600 31q hr %-see m' hr where 0.017 is determined from containment Icakage rate vs pressure curve from Reference 2.13 for an assumed 1 psig. 3.4E-3 la from Reference 2.12.

O

, DUKE POWER COMPANY

, . CATAWBA NUCLEAR STATION EDA-2 ENCLOSURE 5.10 (r~~}j CONTAINHENT LEAKAGE RATE VERSUS PRESSURE AND SIZE OPENING Por 1" diameter opening PSIG ml/hr PSIG ml/hr PSIG ml/hr

>1.25 2.209E8 >5.0 3.908E8 >12.5 5.862EB

>2.50 2.889EB >7.5 4.588E8 >15.0 6.287tB

>3.75 3.483E8 >10.0 5.268E8 For 2" diameter cipening PSIG ml/hr PSIG ml/hr PSIG ml/hr

>1.25 8.496L8 >$.0 1.512E9 >12.5 2.243E9

>2.50 1.12109 >7.5 1.784E9 >15.0 2.464E9

>3.75 1.342E9 >10.0 2.022E9 For 4" diameter opening PS1G ml/h r PSIG ml/hr PSIG ml/hr

->1.25 3.144E9 >5.0 5.692E9 >12.5 8.496E9

~>2.50 4.21.BE9 >7.5 6.797E9 >15.0 9.176E9

>3.75 5,0'18E9 >10.0 7.731E9 Tor 6" diameter opening

() PSIG ml/hr PSIG ml/hr PSIG ml/hr V >1.25 7. 'l3 7E9 >5.0 1.291E10 >12.5 1.93/E10

>2.50 9.516E9 >7.5 1.529E10 >15.0 2.124E10

>3.75 1.138E10 >10.0 1.716E10 ,

For 8" 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 1.648E10 >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 PSIG .nl/hr PSIG ml/hr PSIG ml/hr

~

>1.25 5.522E10 >5.0 1.003E11 >12.5 1.529E11 ,

>2.50 7.476E10 >7.5 1.189E11 >15.0 1.665E11 '

>3.75 2.836E10 >10.0 1.351E11

EDA-2 Enclosure 5'.10

. Page 2 of 2 l'or 34" diameter opening O PSIG ml/hr PSIG ml/hr PSIG ml/hr

>1.25 1.869E11 >$.0 3.398 Ell >12.5 5.132E11

>2.50 2.583E11 >?.5 4.078E11 >15.0 5.607E11

>3.75 3.093E11 >10.0 4.588E11 l For Personnel llatch opening l PSIG ml/hr PSIG ml/br PSIG ml/hr !

>1.25 2.379E12 >5.0 4.690E12 >12.5 6.967E12

>2.50 3.398E12 >7.5 5.573E12 >15.0 7.646E12

>3.75 4.111E12 >10.0 6.372E12 I

For Equipment flatch opening PSIG ml/hr PSIG ml/hr PSIG ml/hr

>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

Enclosure 5.10 is the containment leakage for an opening size in standard cubic feet per min (sefs) x 2.83E4 ml/f t8 x 60 min /hr.

O O

~

y, DUKE POWER COMPANY

, CATAWBA NUCLEAR STATION EDA-2 g ENCLOSURE 5.11 SOURCE TERM ASSESSMENT - UNIT YENT Report (/

Reactor Trip __ _ / Projection based on data on _ /

(Date/ Time) (Date/ Time)

Calculations based on Melted Core LOCA C Fil = ,, f t ' *t.in i

NOBLE GAS ,

based on (checit one) o EHF36(L) if < 1E7 cpm o EHF36(ll) If > 100 cpm o EHF54 if 36(H) is offscale

-EHF CF CFH Q gg epm or R/hr x x Lt * =

1 (Encl. 5.12) min see based on Unit Vent Sample pCi/ml x 4.72E-4 _C1 min C x f,1 s ,

,,,g,g sec f t* pC1 min sec es IODINE

-( based on-O 01 NG .

G.i x 1131 eqv./Xe133 eqv. =

1 sec ratio (Encl. 5.6) see based on CTH EHF37 Apfj x 1.33E-13 Ci min min x Lt *, =

Q.1 Amin sec ft* cpm min see based on Unit Vent Sample pC1/ml x 4.72E 4 Ci min ml x f,1 8 = ,0,,1 sec ft* pCi min sec

('

o Emergency a Drill Prepared by:

~, EDA-2 ~

/~'T DUKE [' l k/

s ENC

'l COMPARY

.iE 5.12 (s ,

CATAWBA UNIT VENT NOBLE GAS CORRECTION FACTOR *

Time 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 2.358E-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 fus7 Accident (less than 100 days old) use 2.358E-11 for EMF 36(L), use 9.67E-8 for EMF 36(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 EMFI4.

Units in Ci min units in Ci min units in Ci min sec ft' cpm sec ft' cpm see it' R/hr Enclosure 5.12 is the correlation factor per Reference 2.13 x 2.83E4 e1 x min x Ci ft' 60 see IE6 pCi

DUKE POWER COMPANY

,, CATAh'DA NUCLEAR STATION

,, EDA-2

, . ENCLOSURE 5.13 INTEGRATED DOSE f

'n Duration (hrs) _

A0 B1 El Al Cl D1 F1 B2 A2 C2 D2 ---.

<G

's _ ) E2 F2 F3 A3 Instructions:

1) Add the doses from previous releases to the projected release,

2) Add the times of releases to the time of the projected release.

l l

.[h

(_)

-. . . . -- __ _ .a

ML20072T695

Contents

Text

2 x = 33.6 x TQ NG 2 M x 2.26E6 = x 2a 2x = 33.6 x TQ gg -- 5 : - TQ .x 2.26E6:= -x 2

2 x _ = 33.6 x TQ NG 4 % x 2.26E6 = x 2= i 2 x ,_ 'M x 2.26E6

31.6 x TQ NG 7 x 2

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ML20072T695

Text

2 x = 33.6 x TQ NG 2 M x 2.26E6 = x 2a 2x = 33.6 x TQ gg -- 5 : - TQ .x 2.26E6:= -x 2

2 x _ = 33.6 x TQ NG 4 % x 2.26E6 = x 2= i 2 x ,_ 'M x 2.26E6

31.6 x TQ NG 7 x 2

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