ML20081K010

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Rev 8 to EDA-3, Offsite Dose Projections for McGuire Nuclear Station
ML20081K010
Person / Time
Site: Oconee, Mcguire, McGuire  Duke Energy icon.png
Issue date: 06/06/1991
From: Harris R
DUKE POWER CO.
To:
Shared Package
ML15224A894 List:
References
EDA-3, NUDOCS 9106240343
Download: ML20081K010 (30)
v • d • e


Text

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4 CRISIS MANAGEMENT PLAN IMPLEMENTING PROCEDURE EDA - 3 "Off-Site Dose Projections for McGuire Nuclear Station" Y JJud Approved By 66/7/

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Rev. 8 June 6, 1991 9106240343 910617 PDR ADOCK 05000269 F PDR d

EDA-3 0FF-SITE DOSE PROJECTIONS FOR MCGUIRE NUCLEAR STATION

1.0 PURPOSE

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 valven, during an emergency. Where appropriate, the Dose Assessment Coordinator, or designee, may deviate from this procedure due to varying plant conditions.

2.0 REFERENCES

2.1 HP/0/ B /1003/08, Determination of Radiation Monitor Setpoints (EMF's) .

2.2 HP/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 Technical Specifications.

2.4 HP/1/B/1009/15 and HP/2/B/1009/15, Post-Accident Containment Air Sampling System Operating Procedures.

2.5 HP/0/ B /1009/06, Procedure for Quantifying High Level Radioactivity 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 Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I".

2.10 NuReg-0396, EPA 520/1-78-016, " Planning Basis for the Development of State and Local Government Radiological Emergency Response Plans in Support of Light Water Nuclear Power Plants".

2.11 NuReg-0654, FEMA-R EP-1, Rev .1, " 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 from McGuire and Catawba Nuclear Station.

3 1

, 1 2.13 McGuire Nuclear Station Class A Computer Model Validation.

3.0 LIMITS AND PRECAUTIONS:

3.1 This procedure is an alternative method of dose at.sessment 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 fodine release is very small compared to the thyroid dose; therefore, lodine whole body dose is not considered here.

3.4 This procedure considers all releases to be ground level releases and that all meteorological data are 15 minute 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 assessment group, shall be compared with those calculated by the CMC before an evacuation recommendation is made.

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

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

4.0 PROCEDURE

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

4.1 Meteorology Assessment 4.1.1 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.

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. 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 can not be obtained from plant systems, obtain them from the National Weather Service (phone 359-8284). If the NWS information is unavailable, then obtain data from the CNS Control Room (8-831-2338).

4.1.1.3 Temperature gradient (AT) in degrees contigrade.

4.1.1.4 Using Enclosure 5.3, determine the stability class based on AT. If AT is unknown, then the following applies:

4.1.1.4.1 If between 1000 - 1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br />, use stability class D; 4.1.1.4.2 If between 1600 -

1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br />, 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 parameters , XTQ (sec/m3 ), for .5, 2, 5 and 10 miles (record on Enclosure 5.1).

4.1.2.1 Using AT, deterndne the two hour relative concentration value (C,i) from Enclosure 5.3.

4.1.2.2 Convert the Cri values to X/Q:

C" XIQ =

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.

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-4 4.1.4 Recheck meteorological conditions approximataly every 15 minutes to ensure that other zones have not been affected.

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

NOTE: Much of the information for Steam Rollef Valve source term assessment can be obtained from the OAC (General 19 program) . See Enclosure 5.14 for instructions.

4.2.1 Determine the Sub-Noble Gas Release Rates, SQ30 (C1/sec), by the following method:

4.2.1.1 For Unit 1 -

EMF 24, EMF 25, EMF 26 and EMF 27 For Unit 2 -

EMF 10, EMF 11, EMF 12, and EMF 13 SQm -

mMhr x x LBM x CF where:

mP./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 CF =- the correction factor per Enclosure 5.6 Ibm Rhr 4.2.2 Determine the Noble Gas Release Rate, Q30 (Ci/sec):

Q.so SQso (IEMF24 or 2 EMF 10) +

i SQso (IEMF25 or 2 EMF 11) +

SQso (IEMF26 or 2 EMF 12) +

SQso (IEMF27 or 2 EMF 13) 4.2.3 Determine the Iodine release rate, Qi (Ci/sec):

. Q, c Om x I/Xe ratio where:

1/Xe ratio = ratio of I-131 eqv./Xe-133 eqv. from Enclosure 5.7 4.2.4 Record Q30 and Q 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 assessment can be obtained from the OAC (Tech Spec 04 program) . See Enclosure 5.14 for instructions.

4.3.1 Determine the Noble Gas Release Rate, Q3o (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, where; Om = EMF x CF x LR where:

EMF = 39(L), if EMF 39(L) < 1E7 cpm, EMF = 39(H), if EMF 39(L) is offscale and EMF 39(H) > 100 cpm, EMF = 51A or 51B; if EMF 39(H) is offscale CF = the correction factor per Encloaura G.9 LR = Leak Rate, (ml/hr) by one cf the following methods:

based on containment pressure:

LR = RLR (from Enclosure 5.10) based on an opening in containment:

LR = OIC (from Enclosure 5.11) l l

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.a.

based on design leak rate:

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i LR = 1. 714 E5 (reference 2.13) 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, x CF x LR Where:

Conc = the Xe-133 equivalent concentration (pCl/ml) from Reference 2.4 or 2.5 CF = 2.78E-10 Cl hr sec pCI LR = icak rate, as determined in step 4.3.1.1 above 4.3.2 Determine the Iodine Release Rate Qi (C1/sec), based on one of the following methods:

4.3.2.1 Based on QNoi O, = O m x I/Xe rado where:

QNa

= 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.

4.3.2.2 Based on EMF 40:

O, , aCPM ,g,54g_gg Cl W min , (g amin sec ml cpm where:

ACPM = reading from EMF 40

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. 7 j Amin = the time interval for EMF 40 observation (normally 15 minutes)

LR = leak rate as determined in step 4.3.1.1 above G.54E-20 = (4.0E-5 pCi/ cpm x .1667 min /ft3 x 3.53E-5 ft 8 /ml x 1C1/1E6 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 ,y O, = Conc x 2.78E-10 sec pC/

where:

Conc = I-131 equivalent concentration (pCi/ml) f cm Reference 2.4 or reference 2.5 LR = leak rate as determined in step 4.3.1.1 above 4.3.3 Record Qsa 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 can be obtained from the OAC (Tech Spec 04 program). See Enclosure 5.14 for instructions.

4.4.1 Determine the Noble Gas Release Rate, QNa (C1/sec), based on one of the following methods:

4.4.1.1 Based on an EMF reading, where NOTE: See Limit and Precaution 3.8.

Om = EMF x CF x CFM

. where:

EMF = 3G(L) if EMF 36(L) < 1E7 cpm EMF = 3G(11) if B1F36(L) is offscale and B1F36(ll) is > 100 cpm EMF = 36(IIII) if EMF 30(II) is offscale CF = the correction factor per Enclosure 5.13 CFM = unit vent flow rate (ft /3 min) 4.4.1.2 Based on unit vent sample, where; Om = Conc x CF x CFM where:

Cone = the Xe-133 equivalent concentration (pCi/ml) from Reference 2.5 C/ min mi CF = 4.72E-4 sec /t8 pC/

CFM = Unit vent flow (ft /8 min) 4.4.2 Determine the lodine Release Rate Qi (Ci/sec) based on one of the following methods:

4.4.2.1 Based on Qso; Q, = Qw x IXe rak where:

Qso

= noble gas release rate as determined in step 4.4.1 above I/Xe ratio = ratio of I-131 eqv./Xe-133 eqv. from Enclosure 5.7 4.4.2.2 Based on EMF 37:

6 CPM / *I" * "

x CFM Q, = 1.11 E-13 amin secIt8 cpm where:

. . , -~ . - . . - - - . . - .- . .. . - -

'(

__. ACPM'- reading from EMF 37 Amin = the time interval for EMF 37 observation (normally 15 minutes)

CFM = unit. vent flow (fts/ min) 1.11E-13 = (4.0E-5 pCi/ cpm x .1667 min /ft8 x 1 C1/1E6 pCi -x 1 min /60 sec) 4.0E = correlation factor for EMF 37 from Reference 2.1

.1667 min /ft8 = inverse of EMF flow rate 4.4.2.3 Based on unit vent sample:

O, = Conc x 4.72E-4 Cl min ml , cpy sec tt' pCI where: -

Conc = I-131 equivalent concentration (pC1/ml) from Reference 2.5 CFM = unit vent flow rate (ft /3 min)

'4.4.3 Record QNo and Qi from the unit. vent on Enclosure 5.1.

- 4.5- Dose Assessment (Enclosure 5.1)

! 4.5.1 Determine the total Noble Gas and Iodino Release Rates (TQsa and TQ i) by-summing Q3o 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:

N DRwb = MD x tow _ x 33.6 1

< where:

33.6 is the_-adult whole body dose _ conversion fac+or from i 8

- Reference 2.9 in . Rom m hr C1 4.5.3 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 <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> time period 4.5.4 Determine the Projected Child Thyroid Dose Rate, DRet (Rem /hr), due to iodine for .5, 2, 5 and 10 miles:

DRct = WQ = TO, x 2.26E6 where:

2.26E6 is the child thyroid dose conversion factor from Reference 2.13 in Rem ma hr Cl 4.5.5 Determine the Projected Child Thyroid Dose, Det(Rem), due to lodine for .5, 2, 5 and 10 miles:

Oct = DRct x 2 hr where:

dose is integrated over 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> time period 4.6 Protective Action Recommendations (Enclosure 5.1, page 2 of 2):

4.6.1 Record the next sequential report number.

4.6.2 Determine release status by the following guidance criteria:

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

Potential Release - activity generated by the event that can potentially be released, but is not currently being released.

Release Within Normal Operating Limits - activity generated by the event currently or previously released within normal l

operating limits (below 1.711E-1 mrem /hr child thyroid and/or 1.008 E-2 mrem /hr whole body) . Examples include containment l

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pressure > 1psig with increased reactor building activity, SIG l 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

'he event currently or previously released nbove normal operating limits (above 1.711E-1 mrom/hr child thyroid and/or 1.008E-2 mrem /hr whole body).

NOTE: Tech. Spec normal operating limits (most limiting values) are derived below.

1.711E-1 mromlhr = 1500 mremlhr x yrl8766 hr.

1.008E-2 mrom/hr = 3E-7 pCI , 33,gremlhr , Cl ,

1E6ml , 3 g3 mmm ml C//m 8 1E6pCl m8 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 thyrold, then recommend no protective action (action A).

4.6.5 If the projected dose in a PAZ is 1 - 5 Rem whole body or 5 - 25 Rem thyroid, then recommend evacuation of children and pregnant women (unless constraints make it impractical) and shelter others (action 11 and E).

4.6.6 If the projected dose in a PAZ is > 5 Rem whole oody or > 25 Rem thyroid, then recommend evacuation of affected zones and shelter all remaining zones (action C).

4.6.7 If the dose rato at the site boundary is > 5.0E-4 Rem /hr whole body, then recommend an Alert.

4.6.8 If the dose rate at the site boundary is > .05 Rem /hr whole body or > .25 Rem /hr thyroid, then recommend a Site Area Emergency if readings last 30 minutes.

. 4.6.9 If the dose rate at the site boundary is 1 5 Rom /hr whole body or 1 2.5 Rem /hr thyroid, then recommend a Site Area Emergency if readings last 2 minutes.

4.6.10 If the dose rate at the site boundary is 11 Rem /hr whole body of15 Rem /hr thyroid, then recommend a General Emergency.

5.0 FNCLOSURES

5.1 Dose Assessment Report 5.2 Meteorology Worksheet 5.3 Two-hour Relative Concentration Factors (CH )

5.4 Protective Action Zones Determination 5.5 Source Term Assessment - Steam Relief Valves 5.6 EMF 24, EMF 25, EMF 26, EMF 27 or 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 Leakage Rate versus Pressure and Size Opening 5.12 Source Term Assessment - Unit Vent 5.13 Unit Vent Monitors - Correction Factors 5.14 OAC Instructions l

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,- EDA-3 ,

Enclosure 5.1 McGUIRE NUCLEAR STATION DOSE ASSESSMENT REPORT

. Unit Report i o R cctor Trip / Projection based on data on /

! (date/ time) (date/ time) 1 Prop 3 red by:

AfeteorO/Ogy Assessmafft ( ) Current [ ] Hypothetical Wind Speed sph Wind Direction degrees from North Temperature Gradient (AT) _ C stability Class A C D E F G Milco 0-2 2-5 5 - 10 PAZ LBMC NAD0R EFGHIJKPQS I

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l- Tctal Source Term Assessment ( ) Current ( ) Hypothetical Steam Relief Containment Unit Vent Total (C1/sec)

Enciocure 5.5 Enclosure 5.8 Enclosure 5.12 C1/sec + Ci/sec + C1/sec =- =

TQ,,

C1/see + C1/see + C1/sec = = TQ 3

- Done Assessment C" .

c )lTQ WS

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$---< Adult whole body <---< . _ __ >---> Child thyroid >---> -

2 hr 2 hr Dozo <--< - 2 x DRwb <--< 33. 6 x TQ,, x X/Q X/Q X70 x TQ - x 2.26E6 >--> DRet x 2 >--> Dose (rom) (rem /hr)- (Ci/sec) (sec/m3 ) (C1/sbc) (rem /hr) (rem) ~

Distance -

TQ,, miles TQ g

2x = 33.6 x .5 x 2.26E6 = x2

2 x' = 33.6 x 2 x 2.26E6 = x2

2x = 33.6 x 5 x 2.26E6 = x2

2x = 33.6 x 10 -- x 2.26E6 = x2

=2x = 33.6 x 1 x 2.26E6 = x2=-

2x = 33.6 x- 4 -- x 2.26E6 = x2

2x = 33.6 x 7 x 2.26E6 = x2

2x = 33.6 x 8 x 2.26E6 = x2

Field Data l

Adult whole body Child thyroid Location ' Dose Rate 2hr Dose Location Dose Rate 2hr Dose Rem /hr Rem Rem /hr Rem

[ ] Emergency ( ) Drill l-

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EDA-3 l Enclosure 5.1 Page 2 of 2 McGUIRE NUCLEAR STATION DOSE ASSESSMENT REPORT To: Emergency Coordinator Report #

The Emergency Condition:

(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 in not currently being released.

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

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

Started Stopped In progrees The following protective actions are recommended:

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

(Less than 1 Rem Whole Body and less than 5 Rem Thyroid)

B) Remain indcore with windows closed, turn off air conditioners and other ventilation, monitor EBS stations. Control acceso. (Action E also)

(1-5 Rem Whole Body or 5-25 Rem Thyroid)

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

Control access. (Greater than 5 Rem Whole Body or greater than 25 Rem Thyroid)

E) Pregnant women and children evacuate (unless constrainte make it impractical) and go to designated shelter. (1-5 Rem Whole Body or 5-25 Rom Thyroid)

  • - based on field data Emergency Classification based on Radioloalcal Data

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

[ ] Potential Site Area Emergency if readinge last 20 minutes

[ ] Recommend Site Area Emergency Now, readinge have lasted 30 minutes (Dose rate at 0.5 miles le > .05 Rem /hr Whole Body or > .25 Rem /nr Thyroid)

() Recommend Site Area Emergency if readinge last 2 minutes (Dose rate at 0.5 milen is > .5 Rem /hr Whole Body or > 2.5 Rem /hr Thyroid)

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

Comments:

Dooes concur with CMC 7 (Yea /No/NA)

/

Doce Assessment Coordinator Date/ Time

[ ] Drill

_, EDA-3 Enclosure 5.2 McGUIRE NUCLEAR STATION METEOROLOGY Unita Report #8 Reactor Trips /

Prepared by:

Wind speed (WS) mph 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 G 'C NOTE: If the wind speed or wind direction cannot be obtained from plant i systems, obtain them from the National Weather Service, 359-8284. l If NWS information is unavailable, then obtain data from the Catawba Nuclear Station Control Room, 8-831-2338.

EDA-3 Encloture 5.3 .

McGUIRE NUCLEAR STATION TWO-HOUR RELATIVE CONCENTRATION FACTORS (Cs )

Temperature Stability Distance (Miles)

Gradiant Class

.5 1 2 3 4 5 6 7 8 9 10

1) AT< .6 A 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 2)

.6 s A T < .5 C 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 1.1 E-6 8.3E-7 7.8E-7

3) .5 SAT < .2 D 3.8E-4 1.4 E-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 4)

.2 s A T < +.4 E 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 5)

+ 4 5 AT <+12 F 1.1 E-3 5.1 E-4 2.0E-4 1.2E-4 8.2E-5 G 3E-5 5.1 E-5 4.3E-5 3.8E-5 3.3E-5 3.0E-5 6)

+1.2 s A T G 1.8E-3 1.1 E-3 4.3 E-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 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.

EDA-3 Enclosure 5.4 McGUIRE NUCLEAR STATION PROTECTIVE ACTION ZONES DETERMINATION Determine the atfected zones (based on wind direction) from the table below and record on Enclosure 5.1, N_QlE. If 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 5 - 10 Miles (Degrees from North) 0 - 5 Miles 0 - 22.5 L,B,M,C.D.O.R E.S,F 22.6 - 45.0 L,0,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.O.R,N P,0,S 90.1 - 112.5 L,B,M.C.O.R,N K,P.O.S 112.6 - 135.0 L,B,M.C.O.N,R. A 1,K,P,0,S 135.1 - 157.5 L,B,M,C,0,A,N 1,K,P,0 157.6 - 180.0 L.B,M,C A.N I,J,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,0 G H,l.J K P 225.1 - 247.5 L B M.C, A,D F,G,H,lJ 247.6 - 270.0 L,B,M.C A.D F,G H,1,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

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  • EDA-3 McGUIRE NUCLEAR STATION Enclosure 5.5 SOURCE TERM ASSESSMENT - STEAM RELIEF VALVES Report #

Reactor Trip / Projection based on data on /

(date/ time) (date/ time)

Calculations based on Melted Core LOCA NOitLE GAS based on EMF 24 or EMF 10 mR/hr x 1 x lbm x Ci* = Ci/sec see iba mR/hr

+

based on EMF 25 or EMF 11 mR/hr x 1 x lbm x Ci* = Ci/sec see Ibm mR/hr

+

based on EMF 26 or EhF12 mR/hr x 1 x lbm x Ci* = Ci/sec sec lbm mR/hr

+

based on EMF 27 or EMF 13-mR/hr x 1 x lbm x Ci* = Ci/see see Ibm mR/br

+

Total from all Steam Relief Valves, Q NG '!**

  • From Enclosure 5.6 IODIhT From all. Steam Relief valves Q Ci/sec(Q NG * ~

"9"* *~ *9#' #* ' * ' *#

(Enclosure 5.7)

( } Emergency [ ] Drill Prepared by:

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

, w ,

t EDA-3 Enclosure 5.6 McGUIRE NUCLEAR STATION l STEAM LINE MONITOR  ;

NOBLE GAS CORRECTION FACTOR I EMF 24, EMF 25, EMF 26, EMF 27, or 4 EMF 10, EMF 11, EMF 12, EMF 13  !

Time Since Trip (hrs) Correction Factor

~

20 6.3820 x 10'* I 22 1.1255 x 10 4 )

l

~

4 l 24 1.2763 x 10 l 28 1,4736 x 10 4 4

2 24 1.6476 x 10 2 48 1.6476 x 104 2 100 1,6476 x 104 2250 1.6476 x 104 4

2 500 1.6476 x 10 2 720 1,6476 x 10 4 O'

r

eunits in lbm mRihr -

l 1

e Endosure 5.6 is the correlation factor per Reference 2.13 x 2.83E4 x.

x .41 ,' 1gg g,

.'41 - spedfic volume of steam per Referena 2.13.'

1 I

O

.1 .

EDA-3 Enclosure 5.7 l McGUlRE NUCLEAR STATION  !

l-131 eqv/Xe-133 eqv. Ratio NOTE: For containment releases in which t/Xe ratio is utilized to determine 1-131 equiv. concentration, apply the appropriate correction from the table below.

Column 1 Column 2 Time Since Trip (hrs) Ratio based on LOCA Ratio based on Melted Core 20 2.91 E-3 2.24E-3

_ z2 3.61 E-3 9.66E-3

-2 4 4.05E-3 1.59E-2 28 4.64E-3 2.85E-2 2 24 5.08E-3 7.52E-2 284 -5.11E-3 1.11 E-1 2 100 5.42E-3 1.33E-1 2 250 7.00E-3 1.80E-1 2 500 1.09E-2 2.90E-1 2 720 1.53E-2 4.33E-1

  • Enclosure 5.7 is from Reference 2.13.

NOTEi 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 (based on LOCA).
2. LOCA throuoh charcoal filters. divide column 1 value by 100.
3. Core damace. use column 2 (based on Core Melt).

.- 4. ' Core damaae throuoh charcoal filters. divide column 2 values by 100.

5.~ Tube rupture. use 1.53E-5.- (Column 1 va ue at a 720 hrs, divided by 1000).

6.- New fuel accident (< 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> old), use 2.217E-4. (Column 2 value at a 100 hrs. divided by 600).

. 7. Old fuel accicent (> 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> old), use 7.217E-4. (Column 2 value at z 720 hrs, divided by 600).

8. - Gas decay tank. assume no radiciodine released, only noble gases are considered to be released from gas tank.

NOTE: For Etgarn release In which t/Xe ratio is utilized to determine 1-131 equiv. concentration, apply the appropriate correction from the table below:

1: Desion basis crimary coolant. divide column 1 value by 100.

2. lodine soiked crimary coolant. use column 1.
3. Core damaae. divide column 2 value by 100.

a

,g v .' .

EDA-3 Enclosure-S.8 HbGUIRE NUCLEAR STATION SOURCE TERM ASSESSMENT - CONTAINMENT Report #

^ Reac t o r .-Trip / Projection based on datn on /

(date/ time) ,,

(date/ time)

Calculations based on Melted Core LOCA Containment pressure psig LR_ = ml/hr LR' based on: Realistic Leak Rate Opening in Containment Design Leak Rate

.(circle-one) Opening size: (1.714E5) assuming bypass leakage of 0.07 NOBLE GAS based on (check one)-

EMF 39(L) EMF 39(H) EMF 51

( ) if < IE7 cpm [ ] if > 100 cpm ( ) if 39(11) is offscale

-EMF- CF LR Q NG cpm or x- x ml/hr =

C1

, R/hr (Encl. 5.9) sec based on-PAGS sample pC1/ml. x 2.78E-10 C1 hr x mE/hr = Ci sec-pCi nec l-t

, IODINE-l based-'on 9NG 9I Ci x- I-131 eqv./Xe-133 eqv. = Ci sec ratio-(Encl. 5.7) see based on LR EMF 40 acpm x- 6.54E-20 Ci hr min x =

ml/hr Ci

. Amin -sec-mi epm see based =on PAGS sample

,pCi/ml x 2.78E-10 Ci hr x ml/hr =

C__i -

see pCi sec

( ) Emergency-

. [-j Drill Prepared by:

EDA-3L . . .: . ~ '

Enclosure 5.9' .

1 McGUIRE NUCLEAR STATION.

CONTAINMENT MONITORS NOBLE GAS CORRECTION FACTORS EHF39L EMF 39H' EMFSI A'or'H -;

a

' ' Time- Correction . Correction Time Correction ' Correction Time Correction Correction '!

Since Factor- Factor based .Since Factor Factor. based Since Factor Factor bascet Trip based on on Melted Trip. . based'on_ 'on Melted Trip based on on Melted ,

{ (hrs) LOCA Core' (hrs) 'LOCA~ Core (hrs) LOCA Core .

20 6.394E-18 6.672E-17' 10 -5.56E-14 1.'429E-13 >0 3.781E-10 1.190E-9 j

>2 6.394E-18 4.448E-17 >2 5.56E-14 1.003E-13 >2 3.Il4E-10 5.894E-10 ,

l 24 6.394E-18 3.058E-17 >4- 5.56E-14 1.232E-13 >4 2.780E 4.726E-10 l 28- 6.394E-18 .'2.113E-17 >8 5.56E-14 1;195E-13' >8 2.446E-10 3.392E-10  !

, > 24 6.394E-18 1.'ll2E-17 > 24 5.56E-14 7.339E-14 > 24 2.335E 1.890E-10

[ 48 6.394E-18 1.056E-17 [48 5.56E-14 6.060E-14 [.48 2.335E-10 1.668E-10 1 100 6.394E-18 1.390E-17 > 100 5.56E-14 5.699E-14. > 100 2.335E-10 1.612E-10 7

> 250 6.394E-18 1.446E-17 > 250 5.56E-14 5.588E-14 > 250 2.335E-10 1.557E-10' ,

> 500 6.394E-18 9. 730E- l'8 > 500 5.56E-14 5.560E-14 > 500 2.335E-10 1.251E-10

[720 6.394E-18 6.394E-18 [720 5.56E-14 5.560E-14 [720 2.335E-10' l.056E ..

Units in Ci hr ' Units in Ci hr Units in Ci hr i see ml epm .sec al cpm 'sec ml R/hr l[

I

  • ' Enclosure 5.9 is the correlation factor per Reference 2.13 x hr x Ci 3600 sec' IE6 pCi

[

e S

i 1

.. +.... , - . _ . _ _ _ _ _ . . _ _ _ _ _ _ _ _

. : 9. .

EDA-3 Enclosure 5.10 McGUIRE NUCLEAR STATION CONTAINMENT LEAKAGE RATE VERSUS PRESSURE PSIG ml/hr 10 1.460E4 12 3.175E4

>-4 5.821E4

[8 9.779E4 1 10- 1.114E5 1 11 1.164E5 1 12 1.199E5 1 13 1.235E5

> 14 1.260E5 E 15 1.285E5

> 15 Use design leak rate (1.714E5 mg/hr)

  • Enclosure 5.10 is the realistic leakage rate (m 3/sec) per Reference 2.12 x IE6 ml/m3 x 3600 sec/hr x 0.07 (0.07 per Reference 2.6).

.-v

u .

a

  • LDA-3 Encionure 5.11 g McGUlkE NUCLEAR STATION f i CONTAINMENT LEAKAGE RATE VERSUS PRESSURE AND SIZE OPENING for 1" diameter opening PSIG ml/hr PSIG ml/hr PSIG ml/hr

>1.25 2.209E8 >5.0 3.908E8 >l2.5 5.862E8

>2.50 2.889E8 47.5 4.588E8 >l5.0 6.287E8

>3.75 3.483E8 >10.0 5.268E8 for 2" dismeter opening _

PSIG ml/hr PSIG ml/hr PSIG ml/hr

>1.25 8.496E8 >5.0 1.512E9 >l2.5 2.243E9

>2.50 1.121E9 >7.5 1.784E9 >15.0 2.464E9

>3.75 1.342E9 >10.0 2.022E9 For 4" diamecer opening PSIG nl/hr PSIG ml/hr

>1.25 PSIG ml/hr 3.144E9 >$.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 7.731E9 For 6" diameter opening PSIG ml/hr PSIG ml/hr PS10 ml/hr

>1.25 7.137E9 >$.0 1.291E10 >12.5 1.937E10 l

>2.50 9.516E9 >7.5 1.529E10 >l5.0 2.124E10

>3.75 1.13BE10 >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 >l2.5 3.381010

>2.50 1.548E10 >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 PS10 ml/hr

>1.25 2.719E10 >5.0 5.012E10 >l2.5 7.476E10

>2.50 3.738E10 >7.5 5.947E10 >l5.0 8.156E10 l >3.75 4.452E10 >10.0 6.712E10 Fcr 18" diameter opening PSIG ml/hr PSIG ml/hr PSIG ml/hr

>1.25 5.522E10 >5.0 1.003E11 >l2.5 1.529011

>2.50 7.476E10 >7.5 1.189E11 >15.0 1.665r11

>3.75 8.836E10 >10.0 1.351E11 For 34" diameter opening.

PSIG ml/hr PSIG ml/hr PSIG ml/hr

>1.25 1.869E11 >5.0 3.396E11 >l2.5 5.132E11

>2.50 2.583E11 >7.5 4.078E11 >l5.0 5.607 Ell

>3.75 3.093E11 >10.0 4.588E11 For Personnel llatch Opening PSIG ml/hr PSIG ml/hr PSIG ml/hr

>1.25 2.379E12 >5.0 4.690E12 >12.5 6.967E12 32.50 3.395E12 >7.5 5.573E12 315.0 7.646E12

>3.75 4.111E12 >10.0 6.372E12, For Equipment Hatch Opening _

PSIG ml/hr PSIG ml/hr PSIG ml/hr

>1.25 1.121E13 >5.0 2.022E13 >l2.5 3.059E13

>2.50 1.478E13 >7.5 2.379E13 >l5.0 3.398E13-

>3.75 1,767E13 >10.0 2.719E13

  • Enclosure 5.11 is the containment leakage for an opening size in standard cubic feet per min (sefm) x 2.83E4 ml/tt3 x 60 min /hr.

l l.

- _;___,.....a_ .-_ , . _ . - - . . . ~ . _ , _ , . . . , _ . . _ _ . _ _ _ . , ~ , . , _ . , _ . _ _ . , _ _ _ . , . . . . _ _ . _ _ , _ _ . . . - . _ _ . .

. .* s EDA-3 Enclo ure 5.12 Mc0UIRE NUCLEAR STATION SOURCE TERM ASSESSMENT - UNIT VENT Report #

Reactor Trip _ / , Projection based on data on /

(date/ time) (date/ time Calculations based on Melted Core LOCA CFM = ft 3/ sin NOBfL GAS

~

based on (check one)

EMF 36(L) EtiF36(ll) EtiF36(101)

'( ) if < IE7 cpm [ ] if > 100 cpm [ ] if 36(11) is offscale EMF CF CFM QNG cpm or x x ft3 = Ci R/br ( Ecl. 5.13) min He based on Unit Vent Sample pCi/ml x 4.72E-4 Ci min ml x ft3 =

_CJ sec ft3 pCi min see LODINE based on Q I

NG CJ x I-131 eqv./Xe-133 eqv. = Ci see ratio (Encl. 5.7) see based on CFM EMF 37 ocpm x 1.11E-13 C1 min min x ft3 =

CJ Amin see ft3 cpm min see based on Unit Vent Sample pCi/ml x 4.72E-4 Ci min ml x ft3 = Ci sec ft3 pCi min sec

[ ] Emeegency [ } Drill Prepared by:

1

EDA-3 .

Enclosure 5.13 McGUIRE NUCLEAR STATION UNIT VENT MONITORS NOBLE GAS CORRECTION FACTORS l

Correction Factors for Melted Core Correction Factors for All Other Accidents Accidents with or without charcoal.

EMF 36HH based 6

EMF 36L EMF 36H EMF 3bHH Time EMF 36L based EMF 36H based Since on Melted Core on Melted Cnre on Melted Core Accident [ Ci min } see ft3 cpm /} [

Ci min Ci min

\see ft 3 R/i r~}/

\sce ft3 cpm /

Trip Ci min )

3cpm /

[\sec Ci min 3 cpm /

} [\seeCiftmin3 R/br New Fuel 9.676i-8 2.358E-4 (hrs) sec ft ft 2.360E-11

>0 1.133E-10 2.426E-7 1.887E-3

>2 7.552E-11 1.704E-7 1.179E-3 All 0ther

_ 1.086E-11 9.440E-8 2.358E-4 Accidents

>4 5.192E-11 2.091E-7 9.905E-4

[8 3.587E-11 2.030E-7 6.367E-4

  • Accidents include LOCA with or without charcoal. Tr:be

> 24 1.888E-11 1.246E-7 2.931E-4 Rupture, WGDT, and Old Fuel. ( > 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> old) l

> 48 1.794E-11 1.029E-7 2.403E-4 .

> 100 2.360E-11 9.676E-8 2.358E-4 2.454E-11 9.481E-8 2.358E-4

{250

> 500 1.652E-11 9.440E-8 2.358E-4 1.086E-11 9.440E-8 2.358E-4

[720

  • Enclosure 5.13 is the correlation factor per Reference 2.13 x 2.83E4 ml x min x Ci P 60 sec IE6 pCi b

.. -==

.. ==

.' EDA-3 Enclosure 5.14 INSTRUCTIONS ON HOW TO ODTAIN DATA FROM THE OPERATOR AlD COMPUTER OAC

1) Toch Spec 04 Program (Plant Data and Status Summary) a) At the OAC in the TSC or Computer Room, press (Toch Spoc) 04 b) Then press [ Print) and (Entor) c) The report will print out
2) General 19 Program (Main Steam Release Program) a) At the OAC in the TSC or Computer, Room press [Gonoral) 19 b) Then press (Print] and [Entor]

c) Using the arrow pointer keys, highlight

d) The report will print out

_ _ __ _ - _- _-___ ___ - __ _ _ - ____ _ ___________ - _-_ _. __ _ ___ .

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