Text

Rev 10 to Crisis Mgt Plan Implementing Procedure EDA-3. Offsite Dose Projections for McGuire Nuclear Station
	ML20091L805
Person / Time
Site:	Mcguire, McGuire
Issue date:	01/16/1992
From:	Harris R; DUKE POWER CO.
To:	;
Shared Package
ML15224A899	List: ML20091L805; ML20091L808;
References
	EDA-3, NUDOCS 9201280244
	Download: ML20091L805 (30)
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_ _ - _ - _ _ _ _ _ - _ - _ - - - _ _ - - .

CRISIS MANAGEMENT PI AN -

' IMPLEMENTING PROCEDURE EDA - 3 "Off-Site Dose Projections for McGuire Nuclear Station"

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QA/ LOA / 0 / ~ /(6 '- 9 9 Apptoved By Date

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E Rev. 10

January 16, 1992 9201280244 920122 '

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EDA-03 Page 1 of 13 i

DUKE POWER COMPANY l Off-Site Dose Projection for McGuire Nuclear Station g

1.0 PURPOSE

l

1.1-To describe a method for projecting dose commitment from a noble gas.

and/or iodine release, through the containment, the unit vent and/or the steam relief valves, during an emergency. Where appropriate, the Dose Assessment Coordinator, or designee, may deviate from this procedure due to varying plant co aditions.

2.0 REFERENCES

1 IIP /0/ B /1003/08, Determination of Radiation Monitor Sotpoints (EMF's) .

2.2 . IIP /0/ B /1009/02, Alternative Method for Determining Dose Rate Within

- the Reactor Building.

2.3 HP/0/ B /1009/10,- Releases of Liquid Radioactive Material Exceeding .

Selected Licensee Commitments.- [

2.4 ' HP/1/B/1009/15 and HP!2/B/1000/15, Post-Accident Containment Air

- Sampling System Operating Procedures. ,

2.5; HP/0/B/1009/06,' Procedure for Quantifying liigh Level Radioactivity 4 Releases During Accident conditions.-

2.6 McGuire Nuclear Station Technical Specifications 3.6.1.2. '

2.7 Offsite Dose Calculation Manual (ODCM).

- 2.8 . Regulatory Guide 1.4,;" Assumptions Used for Evaluating the 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

-Roittine Releases of Reactor Effluents for the' Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I".

2.101. NuReg-0396, EPA 520/1-78-016,-" Planning Basis for the Development of State and Local Government Radiological Emergency Response Plans l

-in Support of Light Water . Nuclear Power Plants".

l- 2.11 . NuReg-0654, FEMA-REP-1, Rev.1, " Criteria - for Preparation and -

t U 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 from McGuire and Catawba Nuclear Station. ,

O a. . . -. - .. . - , - .,

EDA-03 Page 2 of 13 2.13 McGuire Nuclear Station Class A Computer Model Validation.

2.14 Selected Licenseo Commitment Manual Section 16.11-6.

2.15 Letter from C.D. Ingram: June 7,1989, re: Containment Design Leak Rato Validation.

3.0 LIMITS AND PRECAUTIONS:

3.1 This procedure is an alternative method of doso asserzment to the Class A Atmospheric Dispersion Model computer code.

3.2 This procedure applies to releases made from McGuire 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 lodino release is very small compared to the thyroid dose; therefore, lodine wholo body dose is not considered here.

3.4 This procedure considers al! releases to be ground level releaess and that all meteorological data are 15 minre averages. ,

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

3.6 Once the Crisis Management Center (CMC) has been activated, the doses calculated by the Technical Support Center (TSC) dose assesement group, shall be compared with those calculated by the CMC

-before an evacuation recommendation is made.

.3.7 EMF's 38, 39, and 40 willisola:e on a phase A containment isolation (1 psig in containment) . Therefore, EMF's 3SL, 38H, 39L, 39H, 40 and 48 should not be considered valid when containment pressure is 11 psig. .

3.8 The samplo pump to EMP's 35, 36, and 37 will trip when there is a Trire 1 on EMF 36 HH. Therefore, EMF's 35L, 35H, 3SL, 3611, and 37 should not be considered valid when EMF 36 HH is 1 Trip 1 (usually set at 5-7 R / Hr) .

4.0 PROCEDURE

NOTE: Much of th'e information for the meteorology assessment can be obtained on the OAC, (Tech. Spec. 04 program) . Sao Enclosure 5.14 for instructions.

o 4

L l EDA-03 J Page 3 of 13 4.1 Meteorology Annessamnt .j 4il.1 Acquire the following information and record 'on the Dose Assessment Report and Meteorology Worksheet (Enclosures 5.1 and 5.2 respectively).

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 l upper tower wind direction is not. l available, q 4.1.1.2.2 - If the wind speed or wind direction can ]

not be obtained from plant systems, J obtain thent from the National Weather 3

-Service (phone 359-8284, or unlisted 359-8292).= If the NWS information is ,

unavailable, then obtain data from the -- 3 CNS Control Room (8-831-2338).

4.1.1'.3 Temperature gradient (AT) in degrees centigrade. -

. 4.1.1.4 .Using Enclosure 5,3; determine the stability class

based on aT. If AT is unknown, then the following applios:

4.1.1.4.1 - If - between = 1000 - 1600 hours0.0185 days 0.444 hours 0.00265 weeks 6.088e-4 months , use l stability class D;

--4.1.1 A.2 -If between - 1600 -- 1000 hours0.0116 days 0.278 hours 0.00165 weeks 3.805e-4 months , use r stability class G.

4.1.1.5' - 11 necessary, use forecasted meteorological data for calculating- doses due to changing meteorological conditions.

4.1. 2 .' - Determine -the atmospheric - dispersion parameters, X/Q.

(sec/m3 ), for .5, 2, 5 and 10 miles (record on Enclosure 5.1). - 4

- 4.1.2.1- Using ' AT, determine -the two hour relative.

concentration value (CH) from Enclosure 5.3. '

9

. -- Y . . , . A .* *--o=w m ,w- - - . .%.- r y. - . - , -

r ---,r - , - .- y -

w

. EDA-03 Page 4 of 13 4.1.2.2 Convert the C, values to X/Q:

yrc . C" WS 4.1.3 Using Enclosure 5.4, circle on Enclosure 5.1 the protective action zones (PAZ), based upon wind speed and wind direction.

4.1.4 Recheck meteorological conditions approximately overy 15 minutes to ensure that other zones have not been affected.

4.2 Source Term Assonament - Steam Relief Valves (Enclosure 5.5)

@TE: Much of the information for Steam Relief Valve source term assessment can be obtahied from the OAC (General 19 program) . See Enclosure 5.14 for instructions.

4.2.1 Determine the Sub-Noble Gas Release Rates, SQsa (C1/sec), by the following method:

4.2.1.1 For Unit 1 -

EMF 24, EMF 25, EMP2C and EMF 2" For 11 nit 2 -

EMF 10, EMF 11, EMF 12, and EMF 13 SQm = mRhr x VOPEN x LBM x CF where:

mR/hr : EMF reading Unit 1 = EMF's 24, 25, 26, 27 Unit 2 = EMF's 10,11,12,13 VOPEN = time the valve is open in seconds LBM = lbm released for the time the valve was open l CF = the correction factor },cv l Enclosure 5.6 Units , Cl l

' l lbm mRlhr I

l l

1

o. EDA-03

- Page 5 of 13 4 . 2. '2 Determine the Noblo Gas Release Rate, Qso (Ci/seo):

Qso = SQxa (IEMF24 or 2 EMF 10) +

+

SQ3a (IEMP25 or 2 EMF 11) l SQso (IEMF20 or 2 EMF 12) +

SQso (1 EMF 27 or 2 EMF 13) 4.2.3 Determine the Iodine release rate, Qi (Ci/sec):

Or = Om x IlXe raad where:

1/Xe ratio = ratio of I-131 eqv . /Xe-133 eqv. from Enclosure 5.7 4.2.4 Record Qso and Qi from the steam relief valves on Enclosure 5.1.

4.3 Source Term Assessment - Containment (Enclosure 5.8)

NOTE: Some. of the information for Containment source term assessnont- can be obtained from the OAC (Tech Spoo 04

- program) . See Enclosure 5.14 for instructions.

4.3.1 Determine the Noble Gas Release Rate, QNo (Ci/sec) based on one of the following methods:

NOTE: See Limit and Precaution 3.7.

4.3.1.1 Based on an EMF reading, whero; Qw - EMF a CF x LR where:

EMF = 39(L), if EMF 39(L) < 1E7 cpm, EMF = 3 9 (11 ) , if EMF 39(L) is offscale and ,

EMF 39(H) > 100 cpm,

' EMF = 51A or 51B; if EMF 39(H) is offscale

l l .. EDA-03 Pago 6 of 13 CF = the correction factor per Enclosure 5.9 LR = Leak Rato, (ml/hr) by one of the following methods:

Dased on containment pressure:

LR = RLR (from Enclosure 5.101 Based on an opening in containment:

LR = OIC (from Enclosure 5.11)

Based on design leak rate: ,/

LR = 3.01E5 (reference 2.15) '

assuming bypass leakage of 0.07.

4.3.1.2 Based on PAGS sample or sample collected in accordance with reference 2.5, where; Om = Conc u CF x LR Where:

Conc = the Xe-133 equivalent concentration (pC1/ml) from Reference 2.4 or 2.5 CF = 2.78E-10 CI LR = leak rate, as determined in step 4.3.1.1 above 4.3.2 Determine the Iodine Release Rate Qi (Ci/sec), based on one of the following methods:

4 , . 2 .1 Based on Q3a; Q, = Om n I/Xe ratio where:

Q3o

= noble gas release rate as determined in Step 4.3.1 above I/Xe ratio = ratio of I-131 eqv./Xe-133 eqv. from Enclosure 5.7.

k',

.- EDA-03 Page 7 of 13 4.3.2.2- Based on EMF 40:

O, . aCPM ,g$4g_gnsoo j hrmb ml cpm , (g amin where:

ACPM = reading from EMF 40 Amin = the time interval for EMF 40 observation (normally 15 minutes)

LR = leak rate as determined in step 4.3.1.1 above ^

6.54E-20 = (4.0E-5 pCl/ cpm x .1667 min /ft3 x 3.53E-5 fta/ml x 1Ci/IE6 pCi x 1 hr/3600 sec) 4.0E-5 = correlation factor for EMF 40 from Reference 2.1

.1667 min /ft8 = inverse of EMF flow rate 4.3.2.3 Based - on PAGS ' sample or sample collected in accordance with reference 2.5.

CI hr , gg i

Q, Conc x 2.78E-10 sec pCI where:

Conc = I-131 equivalent concentration (pCI/ml)

from Reference 2.4 or reference 2.5 LR = leak rate as determined in. step'4.3.1.1 above 4.3.3 Record QNa and Qi from containment on Enclosure 5.1.

4.4 Source Term Assessment - Unit Vent (Enclosure 5.12)

NOTE: Some of the information for Unit Vent source term assessment cast be obtained from tha OAC (Tech Spec 04 program). See Enclosure 5.14 for instructions.

. EDA-03 Page 8 of 13 4.4,1 Determine the Noble Gas Release Itute, Qyo (Cf /sec), based on ono of the following methodst 4,4.1.1 Bar,ed on an EMP reading, where NOTE: See L!mit and Procaution 3.8.

Om ~-EMF x CF > CPM where:

EMF = 36(L) if EMF 30(L) < 1E7 cpm EMF = l16(11) if EMP36(L) is offocale and EMP36(h) is > 100 epm EMF = 36(Illl) If EMF 3S(ll) is offscale CF = the correction factor per Eneiosure 5.13 CFM = un.t veat f}ow tme (fts/mhi)'

4.4.1.2 Based on uait vont sample, where; Om - Coru: x CF x CFM where:

Conc = the Xe-133 equivalent concentration (pC1/ml) from Reference 2.5 CI = 4.72E-4 seo /t* pCI CFM = Ur.it vent flow (ft 8/ min) 4.4.2 Determine the lodine Release Rate Qi (C2/s, brised on one of 3

the following methods:

4.1.2.1 Based on Q3a; Q, = Om x $Xe ratio where:

Qso

= noble gas release rate as determined in step 4.4.1 above

f i

EDA-03 Page 9 of 13 j 1/Xe ratio = ratio of I-131 eqv./Xe-133 eqv. from Enclosure 5.7 .

4.4.2.2 Based on EMF 37:

O, - ^C## x 1.11 6-13 0 *I"

h x CFM Amin sec tr8 cpm where:

ACPM = reading frota EMF 37 Amin = the time interval for EMP37 observation (normally 15 minutes)

CFM = unit vent flow (ft /8 min) 1.11 E = (4.0E-5 pC1/ cpm x .1667 min /ft 8 x 1 Cl/IE6 pCi x 1 min /60 sec) 4.0E-5 = correlation factor for EMF 37 frotn Reference 2.1

.1667 min /ft3 = inverse of EMF flow rate 4.4.2.3 Based on unit vent samplo:

Q, = Conc x 4.72E-4 0 *U "I x CFM sec /t* pCI where:

Conc = I-131 equivalent concentration (pCi/ml) from Reference 2.5 CFM = unit vent flo rate (ft /8 min) 4.4.3 Record Qsa and _Qif rom the unit vent on Enclosure 5.1.

4.5 Doso Assessment (Enclosure 5.1) 4.5.1 Determine the total Noble Gas and Iodine Release Rates (TQ3a and TQi) by summing Qxa and Qi from all releases.

4. 5. 2- Determine the Projected Whole Body Dose Rate, DRwb (Rem /hr), due to noble gases for .5, 2, 5 and 10 miles:

Rem m3 DRwb - MQ x TQm x 33.6 hr Cl

+ EDA-03 !

.Page 10 of 13 where:

33.G is tho adult wholo body dose conversion factor from N

Reference 2.9 in 4.5.3 Determine the Projected Whole Body Dose, Dwb (rem), due to noblo gases for .5, 2, 5 and 10 miles:

Dwb = DRnb 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 4.5.4 Determine the Projected Child Thyroid Dose Rate, DRet (Rem /hr), due to lodine for .5, 2, 5 and 10 miles:

DRct = WO u 70, x 2.26E6 _R where:

2.2GE6 is the child thyroid dose conversion factor from N

Reference 2.13 in 4.5.5 Determine the Projected Child Thyroid Dose, Det(Rem), due to lodine for .5, 2, 5 and 10 miles:

Dd = - DRct 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 4.6 Protective Action Recommendations (Enclosure 5.1, page 2 of 2):

4.6.1 Record the next sequential report number.

4.G.2 Determine release status by the following guidance criteria:

No Release - no potential release of activity generated by the event.

EDA-03 Page 11 of 13 Potential Release - activity generated by the event that can potentially be released, but is not currently being released.

Release With!n Normal Operating Limits - activity generated by the avent currently or previously released within normal operating limits (bolow 1.711E-1 mrem /hr child thyroid and/or 5

1.008 E-2 mrem /hr whole body) . Examples include containment pressure > 1psig with increased reactor building activity, S/G tube leak, increased unit vent activity, and field team activity.

NOTE: No dose projections to the state / counties are ,

required for this case.

Release Above Normal Operating Limits - activity generated by the event currently or preilously released above no'. mal operating limits (above 1.711E-1 mrom/hr child thyroid and/or 1.008E-2 mrom/hr whole body).

O FOTE: Selected Licensee Commitmen; normal operating limits (most limiting values) are derived below.

1.711E-1 mremlhr 1500 mmmlyr x 97/6766 hr.

1.OOBE-2 miemihr - 3E-7 Cl , 33,g remlhr , Cl ,

1E6ml , 3gg mmm mi Clim 3 1E6pCI m mm 4.6.3 Circle the PAZs and the actions for the current and previous protective action recommendations.

4.6.4 If the projected dose in a PAZ is < 1 Rem whole body and < 5 Rem thyroid, then recommend no protective action (acth.a A).

4.6.5 If the projected dose in a PAZ is 1 to < 5 Rom whole body or 5 to < 25 Rem thyroid, then recommend evacuation of children and pregnant women (unless constraints make it impractical) and shelter others (actions C and D).

. EDA-03 Page 12 of 13 4.6.G If the projected dose in a PAZ is 15 Rem whole body or 125 Rem thyroid, then recommend evacuation of affected zones and shelter all remaining zones (actions B and C).

4.6.7 If the dose rate at the site boundary is 15.0E-4 Rem /hr whole body, then recommeind an Alert.

4.6.8 'f the dose rate at the site boundary is 1 05 Rem /hr whole body or Z .25 Rem /hr thyroid, then recommend a Site Area Emergency.

4.G.9 If the dose rate at the site boundstry is 11 Rem /hr whole body of 15 Rem /hr thyroid, then recommend a General Emergency.

4.6.10 Using data on Enclosure 5.1, pages 2 and 3, complete Enclosure 5.1, page 1 " Emergency Notification", items 5,10, 11,12,13,14, and 15.

NOTE: On item 13, list any whole body or child thyroio dose rate less than 0.0001 mrem /hr as " lass than t .ekground" (where 0.0001 is an assumed value based on yearly effluent data). For integrated doses, use Enclosure 5,15 to calculate the total dose from all releases.

4.G.11 Submit the Emergency Notification form to the offsite communicator for radiological recommendations only. -

5.0 ENCLOSURES

5.1 Emergency Notification / Dose Assessment Report 5.2 Meteorology Worksheet 5.3 Two-hour Relative Concentration Factors (Cu) 5.4 Protective Action Zones Det;.rmination 5.5 Source Term Assessment - Steam Relief Valves 5.6 EMF 24, EMF 25, EMF 26, EMF 27 cc EMF 10, EMF 11, EMF 12, EMF 13 Noble Gas Correction Factors (Steam Line Monitors) 5.7 I-131 eqv. /Xe-133 eqv. Ratio 5.8 Source Term Assessment - Containment 5.9 Containment Monitors - Correction Factors 5.10 Containment Leakage Rate versus Pressure 5.11 Containment Leakago Rate versus Pressure and Size Opening l

I

s EDA-03 Page 13 of 13 5.12 Sourco Term Assessment - Unit Vent

-5.13 Unit Vent Monitors - Correction Factors 5.14 OAC Instructions 5.15 Integrated Dose Calculation

EDA-03 EMERGENCY NOTIFICATION Enclocura 5 1 Pegs 1 of 3 li @ THt8 IS A DRILL - @ ACTUALEMEM8ENCY: OiurTiAL OF0Etone - ME8siAst wuMeaR

2. SITE: McCutre Nuc! eat Sta* UNIT;. REPORTED Bt

3. TRAN8MITTAL TIME WE:

- , . / CONFIRMATION PHONE NUMSER: 875*6044 6faste i mm ao n

4. AUTHENTICAfl0N(if Roteirodi:

5.

EMERGENCY CLAS$1FICAT10N: (baaed on radtological conditions on1y)

@ NOTIFICATION OF UNUSUAL EVENT _ @ ALERT @ SITE AREAEMERGENCY @ GENERAL EMERGENCY

. 6. A Emergency Docteruses At @- Termination At TIME /(MTE: / (il B go te nom 16.)

trastern; mm /

ao ry

7. EMERCENCY DESCRIPfl0N/ REMARKS:

8.' PLANT CONDIT10t @ IMPr10V;NG STABLE @ DECRADING

9. REACTOR STATUS: @ SHUTDOWN: TIME /DATE.

(Eastern;

./

men - ca

/__ @ % PONER n

10. EMERGENCY RElf>3E($):

@ NONE (Go tc cern 14 ) POTENTIAL (Go to stem 14 ) IS OCCURRING @ HASOCCURRED "11. TYPE OF RELEASE: O ELEVATED @ GROUND LEVEL

@ A:RBORNE:' Starteu: -/ /- Stoppeo; -/ /

Tens (Eastern) Cat Time (Eastem) Date

@ S00'0L Started' / / Stopped:

. -/ /

- Time (Eastern) Date Time Itastem) Date "12. RELEASE MAGNITUDE: O CURIES PER SEC. CURIES NORMAL OPERATING LIMITS: BELOW DAB 0vE

@ NOBLE GASES @ 10 DINES IODINE / NOBLE GAS RAfl0 (1: avaitablel OTHER "13. ESTIMATE OF PROJECTED OFF3!TE DOSE: O NEW- UNCHANGEO EST1 MATED DURATION: - HRS Whpiesety CMd DYrsid Wholessey CMd Thyrste

, DOSE MATE DOSE RATE DOSE COSE

_ (mrom/ht) (mrom/hr) (mrom) (mromi

_ SITE BOUNDARY

--2 M:LES 5 MILES 10 MILES __

"14. METIOROLDGICAL DATA: A WIND O!RECTION (from) @ SPEE0(mon)

@ STABILITYCLASS @ PRECIPITATION (type)

15. j RECOMMENDED PROTICTIVE ACTIONS: (based-on radiological conditions only)

{ - @ NORECOMMENDEDPROTECTIVE ACTIONS

! e EVACUATE SHELTER IN-PLACE D OTHER -

16. APPfl0VED Bt TIME /DATE: I /

(Namet (Ltle) (Eastern) mm do yy

!! items 8-14 have not changed, only items 17 and 1S-16 are required to be completed.

"Informacon may not De svedeWe os lastlei notificsoons.

Form 34884(R1901

L .

. EDA-03 Encloturo 5.1 McGUIRE NUCLEAR STATION DOSE ASSESSMENT REPORT

< Unit __

Raport i 1

-R0cetor Trip / Projection bar.ed on data on /

(date/ time) (dat.e/ time )

Prepared by:

Meteorology Assessment [ ] Current [ ] Hypothetical Wind Speed mph Wind Direction degrees from North

emperature

. GradGnt (AT) ,C Stability Cla.se A C D E F G M11Gs C-2 2-5 5 - 10 PAS LUMC NAD0H EFGHIJKPQS TCt#1 Source Term Assessment [ ] Current [ ] Hypothetical

CtGam Relief Containment Unit Vent Total (C1/nec)

Enclost.re 5.5 Ecclosuru 5.8 Enclosure 5.12 C1/unc + Ci/sec + C1/sec = =

TQ ,

C1/sec + Ci/coc + C1/sec = = TQ 3 Dose Assessment C" XfD WS

- Adult Whole Body *- - -

-+ Child Thyroid +

--2m -- 318 m *3 w RTO pts FTO x n 2.26E6 - g x 2 --*

g p q

= 2 x = 33.6 r .5 ~~

x 2.26E6 = x 2 =

2 x = 33.6 x 2 x 2.26E6 = x 2

~

= 2 x = 33.6 x 5 ~

x 2.26E6 = x 2 =

2 x = 33.6 -x 10 x 2.26E6

~

x2 =

= 2 x = 33.6 x l- '

x 2.26E6 = x 2 =

= 2 x = 33.6 x ~~~

4 x 2.26E6 = x 2 =

2 x = 33.6 x 7 x 2.26E6 = x 2

2 x = 33.6 x 8 x 2.26E6 = x 2

Fleid Data Adult whole body Child thyroid Loc: tion Dose Rate 2hr Dose Location Done Rate 2hr Done Rem /hr Rem Rem /hr Rem

[ ] Emergency

[ ] Drill

l

. EDA-03 Enclo:uro 5.1 McGUIRE NUCLEAR STATION DOSE ASSESSMENT RdPORT The Emergency Condillon Report #

(a) No release - no potential release of activity generated by the event.

(b) Potential release - activity generated by the event that can potentially be released, but is not currently being released.

(c) Release (within normal operating limits) - activity generated by the event currently or previously released within normal operating limite. (below 1.711 E-1 mrom/hr child thyroid and/or 1.008E-2 mrom/hr whole body)

Started Stopped In progress (d) Release (above normal operating limits) - activity generatr.d by the event, currently or previously released above normal operating linits (above 1.711E-1 mrem /hr child thyroid and/or 1.008E-2 mrom/hr whole body).

Started Stopped In progress The following protective actions are recommended:

CURRENT PREVIOUS MILES PAZ ACTIONS ACTIONS 0-2 L,B,M,C ABCD ABCD 2-5 N,A,D,0,P ABCD ABCD S - 10 E,F,G,H,l J,K,P,0,S ABCD ABCD A) Monitor environmental radiation levels. No specific actions.

(<1 Rem Wnale Body and <5 Rem Thyroid)

B) Evacuate affected zones and seek shelter if immediate evacuation is not possible. Shelter all remaining zones. Monitor environmental radiation levelr .

Control access. (> 5 Rem Whole Body or > 25 Rem Thyroid)

C) Remain indoors with windows closed, turn off air conditioners and other ventilation, monitor EB9 stations. Control access. (Action D also)

(1 to <5 Rem Whole Body or 5 to <25 Rem Thyroid)

D) Pregnant women and children evacuate (unless constraints make it impractical) a id go to designated shelter. (1 to <5 Rem Whole Body or 5 to <25 Rem Thyroid)

- based on field data Emergency Classification based on Radloloalcal Data

[ ] Recommend Alert (Dose rate at 0.5 miles is > .5 mR/hr Whole Body)

[ ] Recccmend Site Area Emergency (Dose rate at 0.5 miles is > .05 Rem /hr Whole Body or > .25 Rem /hr Thyroid)

( ) Recommend General Emergency (Dose rate at 0.5 miles is > 1 Rem /hr Whole Body or > 5 Rem /hr Thyroid)

Comments:

Doses concur with CMC? (Yes/No/NA)

/

Dose Assessment Coordinator Date/ Time

[ ] Emergency

[ ] Drill j l

. EDA-03 Enclecuro 5,2 Page 1 of 1 McGUIRE NUCLEAR STATION METEOROLOGY Unit Report #

Reactor Tript /

Prepared by: _

I l

l Wind speed (WS) mph l Wind direction 'N AT *C Default Data Wind speed (WS) mph 1000 to 1600 hrs. Wind direction 'N Stability Class D *C Wind speed (WS) mph 1600 to 1000 hrs. Wind direction 'N Stability Class c 'C Is NOTE: If the wind speed or wind direction cannot be obtained from plant systems, obtain them from the National Weather Service, 359-8284 or unlisted 359-8292. If NWS information is unavailable, then obtain data from the Catawba Nuclear Station Control Room, 8-831-2338.

EDA-03 Enclosura 5.3 .

Page 1 of 1 McGUIRE NUCLEAR STATION TWO-HOUR RELATIVE CONCENTRATION FACTORS (C)

Temperature Stability Distance (MI:es)

' /

Gradiant Class

.5 1 2 3 4 5 6 7 8 9 10 1.4E-5 1.2E-6 5.9E-7 4.1 E-7 3.2E-7 2.5E-7 2.0E-7 1.9E-7 1.8E-7 1.6E-7 1.5E-7

1) A T < .6 A

.6 s A T < .5 1.5E-4 4.5E-5 1.3E-5 6.3E-6 3.9E-6 2.7E- 6 1.9E-6 1.4 E-6 1.1E-6 8.3E-7 7.8E-7

2) C I .5 SAT < .2 D 3.8E-4 1.4E-4 4.9E-5 2.7E-5 1.7E-5 1.2E-5 9.2E-6 7.3E-6 6.0E-6 5.0E-6 4.3E-6 3)

.2 s A T < +.4 6.9E-4 2.5E-4 9.6E-5 5.5E-5 3.5E-5 2.5E-5 2.0E-5 1.6E-5 . 1.3E-5 1.1 E-5 9.7E-6

4) E

+.4 s A T < +1.2 F 1.1 E-3 5.1 E-4 2.0E-4 1.2E-4 8.2E-5 6.3E-5 5.1E-5 4.3E-5 3.8E-5 3.3E-5 3.0E-5 5)

+1.2 s A T 1.8E-3 1.1 E-3 4.3E-4 2.7E-4 2.0E-4 1.7E-4 1.3E-4 1.2E-4 8.6E-5 7.8E-5 7.3E-5 l

6) G NOTE: If AT is unavailable use: 1000-1600 hours Use Stability Class D 1600-1000 hours Use Stability Class G There is no B Stability Class for McGuire.

l

. EDA-03 f

Enc!osure 5.4 Page 1 of 1 McGUIRE NUCLEAR STATION PROTECTIVE ACTION ZONES DETERMINATION Determino the altected zones (brsed on wind direction) from the table below and record on Enclosure 5.1.

NOTE: 11 wind speed is less than or equal to 5 mph - the affected zones for 0 - 5 miles shall be L,B,M,C,N, A,D,0,R Wind Direction 0 - 5 Miles 5 - 10 Miles (Degrees from North) 0 - 22.5 L , B , M ,C . D,0, R E S,F 22.6 - 45.0 L , B . M .C. D,0, R E,0,S 45.1 - 67.5 L B M.C D.O.R E,0,S 67.6 - 90.0 L,B.M.C.D,0,R N P.O.S , (

90.1 - 112.5 L,B.M C,0,R N K,P,0,S 112.6 - 135.0 L,B,M.C,0,N,R,A 1,K, P .O .S

~

135.1 - 157.5 L.E.M.C,0, A N I,K,P,0 157.6 - 180.0 L.B.M.C. A.N lJ.K,P-180.1 - 202.5 L,B,M C. A.N G,H,1,J K,P 202.6 - 225.0 L,B.M.C.A.N.D G H 1,J K,P 225.1 - 247.5 L,B,M C. A.D F ,G , H ,1,J 247.6 - 270.0 L,B M.C.A,D F,G,H,l.J 270.1 - 292.5 L,B,M,C.A.D E.F,G,H,J 292.6 - 315.0 L,B.M.C. A.D E.F,G 315.1 - 337.5 L,B,M.C,D,R E.F,G 337.6 - 359.9 L,B,M,C,D,R E F.S i 1

. .. . _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ __o

U. .

r.- EDA-03 Enclosure 5.5 Page 1 of 1 McGUIRE NUCLEAR STATION

- SOURCE TERM ASSESSMENT - STEAM RELIEF VALVES Report #

Riactor Trip: / Projection based on data on: _

l

-(date/ time) (date/ time)

Melted Core . LOCA-7 l Calculations based on NOBLE GAS based on EMF 24 or EMF 10.

? mMhr ~x. 1 x //vn x .

Cl* . Cisec l seo Ibm mMhr l

+ I based on EMF 25 or EMF 11-'

__ mMhrw 1 x lbm x ,_.

Cl* . Cfsec

. seo Ibm mMhr

+

. based on EMF 26 or EMF 12 ,

mMhr x . 1 x lbm x cf. . i,fn seo ' lbm mMhr based on EMF 27 or EMF 13 ,

mMhrx ' x Ibm ~x ct. .: _ Cisea.

sec lbm mMhr -

Total from all Steam Relief Valves, Om . C4sec ;

from Enclosure 5.6 IODINE .

, From all Steam Relief Valves .

On C//sec(0.) x l-131 eqv/Xe-133 eqv rab'o - Cll*80 (Endosure 5.7) f O bmergency~ O ~ Drill Prepared By:

-4

..o EDA 03 i

Enclosure S.6 Pa0e 1 of 1 McGUIRE NUCLEAR STATION -

STEAM LINE MONITOR ,

NOBLE GAS CORRECTION FACTOR ;

EMF 24, EMF 25, EMF 26, EMF 27, or EMF 10, EMF 11, EMF 12, EMF 13 n

l Time Since Trip (hrs) Correction Factor t

a0 6.3820 x 10'*

4 a2 1.1255 x 10 4

24 1.2763 x 10 4

_a 8 1.4736 x 10 4

> 24 1.6476 x 10 .

4 5 48 1.6476 x 10 4

a100 1.6476 x 10

a 250- 1.6476 y 10 4 4

> 500 1.6476 x 10 4

5720 1.6476 x 10 t

'I bn mRlbr

.e Enabsum 6.6 is the correladon faaor per Rekonce 2.13 x 2.83E4 $ x.41 W Cl 1R x ,

tts Ibm 1E6 pCI -'1000 mR

.41; ,@ m/ume of steam per Reference 2.13.

0 i

,_ . . ~ . .-

__. _ . _ ._. . ~_ _ _.

6 .

3, EDA-03 Enclosure 5,7 Pa081 of 1 McGUIRE NUCLI!.AR STATION ,

1-131 eqv/Xe.-133 eqv. Ratio - ;

'NOTEi For contA}DatDJ releases in which 1/Xe ratio is utilized to determine 1-131 equiv. concentration, apply r

' the appropriate correction from the table below,

_ . Column.1 991umn 2 '.;

Time Since Trip (hrs) Ratio based on LOCA Ratio based on Metted Core ;

a0 2.91 E 2.24E-3 a2 3.61 E-3 9.66E 3 a4 4.05E-3 1.59E-2 [

a8 4.64E-3 2.85E-2 t 24 5.08E-3 7.52E-2 a 48 5.11 E-3 1.11 E-1 a100 5.42E-3 1.33E-1 a250 7.00E-3 1.80E-1 ,

a 500 1.09E-2 2.90E-1 2 720 1.53E-2 4.33E-1

Enclosure 5.7 is from Reference 2.13.

NOTE: For vent releases in which 1/Xe ratio is utilized to determine 1-131 equiv, concentration, apply the appropriate -

correction from the table below:

1. LOCA, use column 1 (baced on LOCA), .

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

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

i

4. Ggre damaae tnrouah charcoal fillig, divide column 2 values by.100 . +

' 5;

. Tube rnoture, use 1.53E-5 (Column 1 value at 2 720 hrs, divided by 1000).

6. New..fugl accident (< 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months old), use 2.217E-4. (Column 2 value at a 100 hrs. d!vided by 600).

L 7. -: Old fuel accident (n 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months old), use 7.217E-4 (Column 2 value at a 720 hrs. divided by 600).

8.: Gas decay tank, assume no radiolodine released, only noble gases are considered to be released from 7 gas tank.

E NOTE: For steam release in which 1/Xe ratio is utilized to determine I-131 equiv. concentration, apply the appropriate correction from the table below:

.1; Desian basis crimary coolant, divide column 1 value by 100.

2, ~fodine soiked crimary coolant, use column 1.

3. ' Core damaae. divide column 2 value by 100.

i' s: 1 l

- , . EDA-03 Enclosure 5.8 i' Page 1 of 1 McGUIRE NUCLEAR STATION ,

SOURCE TERM ASSESSMENT - CONThlNMENT Report # .i Reactor Trip / Projection based on date on /

(date/ time) (date/ time)- ;

- Calculations based on- _ _ Melted Core LOCA Containment pressure psig LR = ml/hr LR based on: Realistic Lei.k Rate Opening in Containment Design aak Rate ,

- (circle one) Opening size: ? 02Ed assuming bypass toekage of 0.07- ,

NOBLE GAS based on (check one)

EMF 39 (L) . EMF 39(H) EMF 51 O 11 k 1E7 cpm O if > 100 cpm ' O If 39(H) is offscale _;

EMF CF LR Om w x x gy . Cl

'D (End. 5.9) sec based on PAGS sample Cl -

pC4m/ x Cl hr x W hr .

2.78E-10 ,,,

sec pCI IODINE . ,_

based on O, ' O, .

. Cl ' x _ l-131 sqv)Xe-133 syv. = Cl Q rneo (End. 5.7) sea based on EMF 40 LR Appm x x g,545_gg _ Cl hr min Amin _ sec ml cpm m4hr soo

,s based on PAGS sample-pCimi x g,7gg_3 n Cl hr x m4hr = Cl I

sec pCI :sec l

l O Emergency- O Drill Prepared By:

}

?.

I I I M EDA-03 Enclosura 5.9 -

Page 1 of 1 i

I McGUIRE NUCLEAR STATION I

i CONTAINMENT MONITORS NOBLE GAS CORRECTION FACTORS I

l EMF 39L EMF 39H EMF 51 A or B

- . ~ _

Time Correction Correction Tline Correcdon Correction Time Correction Correction Fector Based Since Factor Factor Based Since Factor Since Factor Factor Based en Matted on Melted Trip Based on on Melted Trip Based on Trip Based on LOCA Cars LOCA Core (hrs) LOCA Core (hrs)

(hrs) ' l 556E-14 1.429E-13 a0 3.781 E-16 1.190E-9 l

zO 6394E-18 6.672E-17 20 556E-14 1.003E-13 22 3.114E-10 5.894E-10 z2 6394E-18 4.448E-17 z2 1

556E-14 1.232E-1:1 a4 2.780E-10 4 726E-10 a4 6 394E-18 3.058E-17 a4 2.446E-10 3 392E-10 i

5.56E-14 1.195E-13 28 l l 28 6.394E 18 2.113E 17 28 556E-14 7339E-14 a 24 2335E-10 1.390E-10 2 24 6 394E-18 1.112E-17 a 24 l

556E-14 6.060E-14 a 48 2 335E-10 i.66SE-10 i 2 48 6 394E-18 1.056E-17 a 48 l i

5.56E-14 5.699E-14 a100 2335E-10 1.612E-10 l 2 100 6 394E-18 1390E-17 a100 1557E-10 5.56E-14 5588E-14 z250 2335E-10

> 250 6 394E-18 1.446E-17 2 250 556E-14 5560E-14 a500 2.335E-10 1.251E-10 2 500 6 394E-18 9.730E-18 a500 2335E-10 1056E-10 6.394E-18 6394E-18 2 720 5.56E-14 5.560E-14 3 720

> 720 l

Q hr Unb in -

U#

Ci hr y g g ;g l Units in sec m! mm sec milibr sec mimm

'V Q

Enclosure 5.9 is the correlation factor per Reference 2.13 x

l 3600 sec 1E6 pc

n, _ < .

3 .'- EDA Enclosure Solo Page 1 of1 V

McGulRE NUCLEAR STATION

=

f CONTAINMENT LEAKAGE RATE VERSUS PRESSURE-PSIG ml/hr

>0 1.460E4 1

[2 3.175E4

>4 5.821E4

[, 8 9.779E4

> 10 1.114E5

[ 11 1.164 E5

- > 12 1,199E5

[ 13 1.235ES

> 14 1.260E5 E5 1 1.285E5

> 15 Use design leak rate (3.02E5 mf/hr) 1 4

Enclosure 5.10 is the realistic leakage rate (m 3/sec per Reference 2.12 and

- 2.15) x.'1E6 ml/m' x 3600 sec/br x 0;07 (0.07 per Reference 2.6).

s

EDA-03 Enclosure 5.11 -

Page 1 of 1 McGUIRE NUCLEAR STATION

-CONTAINMENT LEAKAGE RATE VERSUS PRESSURE AND SIZE OPENING For 1" diameter opening PSIG ml/hr =PSIG ml/hr PSIG ml/hr

>125 2209E8 > 5.0 3,900E8 > 12.5 5.862E8

-- >2.50 2A89E8 > 7.5 4.588E8 > 15.0 6.287E8

>3.7b .

3.483E8 > 10.0 5268E8

. Fort'~di2TreYioceming '

PSIG mi/hr PSIG mUhr PSIG 'ml/hr

> 125 - tsAttE8 - > 5.0 1.512E9 > 12.5 2.240E9

> 2.50 1.E t 9 > 7.5 1.784E9 > 15.0 2.464E9

> 3.75 1.342E9 > 10.0 2.022E9 Wdlemoter opening "

PSIG - mUhr PSIG ml/hr PSIG ml/hr

>125 3.144E9 > 5.0 5.692E9 > 12.5 8.406E9

> 2.50 - 4248E9 : > 7.5 6.797E9 > 15.0 9.176E9

> 3.75 5.098E9 > 10.0 7.731 E9 4 For 6" diameter opening -

4 PSIG ml/hr - PSIG muhr PSIG mUhr.

> 1.25 - 7.137E9 > 5.0 1291E10 > 12.5 '1.937E10 t

> 2.50 9.516E9 > 7.5 1.529E10 > 15.0 2.174E10

> 3.75 1.138E10 > 10.0 1.716E10 - .

For 3" diameter opening !

. PSIG mUhr PSIG mkhr PSIG ml/hr

> 125 - 1.257E10 > 5.0 2243E10 - > 12.5 . 3.381 E10 -

> 2.50 - 1.648E10 - > 7.5 2.634E10 > 15.0 ' 168E10

> 3.7S 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 3.733E10_ > 7.5 5.947E10

> 15.0 - 8.156E10 :

> 3.75 4.452E10' > 10.0 8.712E10 For 18" diameter opening PSIG muhr PSIG - m!!hr PSIG ml/hr

> 1.25 . 5.522E10 > 5.0 - 1.003E11 > 12.5 1.529E11

> 2.511 7.476E10 ~ > 7.5 1.1ME11 > 15.0 1.665E11 l > 3.75 ' 8.836E10 > 10.0 -

' 1.351E11

- For 34" diameter opening

. PSIG ml/hr PSIG ml/hr-- PSIG - muhr

> 125 1.869E11 > 5.0 3.398E11

> 12.5 5.132E11 'I

, > 2.50 2.583E11 > 7.5 4.078E11 > 15.0 5.607E).

l > 3.75 3.093E11 - > 10.0 1.588E11 For Personnel Hatch Opening PSIG mvhr PSIG mUhr PSIG ml/hr h

>125 2.379E12 > 5.0 4.C90E12

> 2.50 > 12.5 6.967E12

' 3.398E12 > 7.5 5.573E12

> S.75

> 15.0 7.646E12 4.111 E12 > n10 6.372E12 F5T1yuipment Hatch opening

' PSIG ml/hr PSiG mUhr PSIG mitt l > 125 1.121E13 > 5.0 2.022E13 > 12.5 3a 59E13

> 2.50 1.478E13 > 7.5 2.379E13 > 15,0 3.398E13

> 3.75 1.767E13 > 10.0 2.719E13 Err 'osure8 5.11 is the containment leakage for an opening size in standard cubic feet por mm (scim) 2.8*.24 ml/it x 60 mm/hr.

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

. EDA-03 Enctor,ure 5.12 Page 1 of 1 McGutRE NUCLEAR STATION SOURCE TERM AGSESSMENT - UNIT VENT neport # _

R:actvr Trip __. . Projection based on date on #

(date/ time) (date/ time)

Cciculations based on Moltod Core _ LOCA CFM = . ft'/ min NOBLE GAS based on (chock one)

EMF 36 (L) EMF 36(H) EMF 36(HH)

O if .: 1E7 cpm O if > 100 cpm O 1136(H) is offscale EMF CF CFM Q.

cpm w x x M* = c; D (Encl. 5.13) E M based on Unit Vent Sample Cl

_ pCtml X 4.72E-4

*I" *# x = E 5 soo fra pCl min K) DINE batort on O. O, Cl X _.. 1-131 %4Xe-133 sqv. =

A soo ratio (End. 5.7) soo s

based on EMF 37 CFM A Wn x 1.11 E-13 Clmin min x ffs = ,Ci Amin sec (18 cpm min sea based on Unit Vent Sample pCim/ x 4.72E-4 C/ *I" *# * #*

A sec Its pCl M sec 0 Emergency a Drill Prepared By:

b EDA-G3 '

Enclosure 5.13

! Page 1 of 1 McGUIRE NUCLEA.R STATION UNIT VENT MONITORS NOBLE GAS CORRECTION FACTORS Correction Factors for Melled Core Accidents with or without charcoal Correction Factars for AII Ot!wr Accidents i EMF 36L bata! EMF 366 ' ased EMF 36HH W EMF 36H EMC 3SHH Time EMF 36L on Melted Core on Men %d Core on Mel'ed Core '

Since ' Accident O min O min CT rn:n m

m m '~

Trip '* "' '* N' 3 sec it8 Rtr,

@rs) see ft* com [sec ft corn.

j 1887E-3 New Fuel 2.360E-11 9 676E-8 2.358E 4 20 1.133E-10 2.426E-7 22 7.552E-11 1.704E-7 1.179E-3 (<100 hrs oks) 9 905E-4 AII Other 1.086E-11 3.440E-8 2.358E-4 24 5.192E-11 2.091E-7 3.587E-11 2.030E-7 6267E 4 Acddm e

28

AcG2 s include LOCA wim or wrthout charcea!. Tube Rupture. I 1.888E-11 1246E-7 ' 2.931E 4 .

2 24 1.029E-7 2.405E d WGDT, and Old Fuel (2 100 hotrs oldt j I l 2 48 1.794E-11 2 ^JO 2 360E-11 S 676E-8 2258E 4 2 250 2.4542-11 9.481 E-8 2.358E 4 2 500 1.652E-11 9 440E-8 2358E-4 2 720 1.086E-11 9.440E-8 2.358E 4 Enclosure 5.13 is the correlation factor pu Reface 2.13 x 2.83E4 Y x x 1E6 pC4 tt 8 60 sec

.m:

. EDA 03 Enclosure 6,14 Page 1 of 1 INSTHUCTIONS ON HOW TO OSTAIN DATA FROM THE OPERATOR AID COMPUTER OAC I) ; Tech Spec 04 Progism (Plant Dets and Status Summary) a)- At the OAC in the TSC or Computer Noom, press (Tech Spec) 04 b) Then press (Print] and (Enter) 1

c) The report will ptint out m.

2) General 19 Program (Main Steam Relanse Program) a) At the OAC in the TSC or Computer, Room press (General) 19 b)' Then press (Print] and (Enterl' l I

c). _Using the arrow pointer keys, highlight ' Main Steam Release" and press nnter,

,. ;, d) The report will print out

,, ,..a. , -_n..,-, ,- ,--r, --n---nr .

I EDA-03 Enclosure 5.15 Page 1 of 1 l lNTEGRATED DOSE CALCULATION om.ium<n,.3 L

B '

hA

, C _

N A

D O

R

. 1 E

G H _. _

l J

K P

O S

Instructions:

1) Add the dosos from previous releases to the projected release.

l

2) Add the timos of previous releases to the time of the projected release.

1 i-

. .

ML20091L805

Contents

Text

1.0 PURPOSE

2.0 REFERENCES

4.0 PROCEDURE

5.0 ENCLOSURES

2 x = 33.6 x 2 x 2.26E6 = x 2

2 x = 33.6 -x 10 x 2.26E6

2 x = 33.6 x 7 x 2.26E6 = x 2

2 x = 33.6 x 8 x 2.26E6 = x 2

Navigation menu

ML20091L805

Text

1.0 PURPOSE

2.0 REFERENCES

4.0 PROCEDURE

5.0 ENCLOSURES

2 x = 33.6 x 2 x 2.26E6 = x 2

2 x = 33.6 -x 10 x 2.26E6

2 x = 33.6 x 7 x 2.26E6 = x 2

2 x = 33.6 x 8 x 2.26E6 = x 2

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