ML16231A276

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Rev 7 to Crisis Mgt Plan Implementing Procedure EDA-2, Off-Site Dose Projections for Catawaba Nuclear Station
ML16231A276
Person / Time
Site: Catawba  Duke Energy icon.png
Issue date: 11/08/1991
From: Harris R
SOUTHERN CALIFORNIA EDISON CO.
To:
Shared Package
ML16231A277 List:
References
EDA-2, NUDOCS 9111190170
Download: ML16231A276 (20)
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Text

DUKE POWER COMPANY EMERGENCY DOSE ASSESSMENT MANUAL November 8, 1991 PI 9111190 1-70 911112 PIDR ADOCK 0500041:3 F

PDR

EMERGENCY DOSE ASSESSMENT MANUAL DISTRIBUTION LIST CONTROL NUMBER HOLDER 1

R. E. Harris 2

W. P. Deal 3

W. M. Funderburke 4

C. T. Yongue 5

Caryl Ingram 6

R. E. Sorber 7

Open 8

D. P. Simpson 9

Open 10 J. W. Foster 11 J. E. Cole 12 P. N. McNamara 13 J. J. Honeycutt (ONS CMC Managers Area) 14 R. N. Keener 15 J. J. Honeycutt (MNS/CNS CMC Managers Area) 16 W. B. McRee 17 NRC Document Control Desk (via Helen Froebe) 18-19 NRC Regional Administrator (via Helen Froebe) 20 NRC Resident Inspector-Catawba (via Helen Froebe) 21 NRC Resident Inspector-McGuire (via Helen Froebe) 22 NRC Resident Inspector-Oconee (via Helen Froebe)

I0

TABLE OF CONTENTS EDA-1 Procedure for Estimating Food Chain Doses Under Post-Accident Conditions (Rev. 3)

EDA-2 Off-Site Dose Projections for Catawba Nuclear Station (Rev. 7)

EDA-3 Off-Site Dose Projections for McGuire Nuclear Station (Rev. 9)

EDA-4 Off-Site Dose Projections for Oconee Nuclear Station (Rev. 7)

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

EDA-6 Mesorem, Jr. Atmospheric Dispersion and Dose Assessment Model Users Manual, Version 4A McGuire (Rev. 0)

EDA-7 Mesorem, Jr. Atmospheric Dispersion and Dose Assessment Model Users Manual, Version 4A Oconee (Rev. 0)

EDA-8 Environmental Monitoring for Emergency Conditions for Catawba Nuclear Station (Rev. 6)

EDA-9 Environmental Monitoring for Emergency Conditions for

)

McGuire Nuclear Station (Rev. 9)

EDA-10 Environmental Monitoring for Emergency Conditions for Oconee Nuclear Station (Rev. 1)

November 8, 1991

EDA-4 DUKE POWER COMPANY OFF-SITE DOSE PROJECTIONS FOR OCONEE NUCLEAR STATION 1.0 Purpose This procedure describes 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.

2.0 References 2.1 PT/O/A/230/01, Radiation Monitor Check 2.2 HP/1,2,3/A/1009/17, Operating Procedure for Post-Accident Containment Air Sampling System 2.3 HP/0/B/1009/15, Procedure for Sampling and Quantifying High Level Gaseous, Radioiodine, and Particulate Radioactivity 2.4 ONS Technical Specification, Appendix A, Section 3.1.4 Reactor Coolant System Activity 2.5 Offsite Dose Calculation Manual (ODCM) 2.6 Regulatory Guide 1.4, Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss of Coolant Accident for Pressurized Water Reactors.

2.7 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 2.8 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 2.9 NuReg-0654, FEMA-REP-1, Rev. 1, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants

.2.10 Oconee Nuclear Station Class A Computer Model Validation (File:

NUC-0306) 2.11 Letter from R. P. Todd, 1-3-86, re: R. B. Containment Leak Flow Rate File:

ON-750.25 2.12 RP/0/B/1000/01, Emergency Classification Procedure

EDA-4 Page 2 of 11 3.0 Limits and Precautions 3.1 This procedure is an alternative method of dose assessment to the Class A Atmospheric Dispersion Model Computer Code.

3.2 This procedure applies to releases made f-rom Oconee 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 iodine release is very small compared to the thyroid dose, therefore this procedure does not consider iodine whole body dose.

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

3.5 Once a sector has been added to the list of affected sectors, 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, should be compared with those calculated by the CMC before a protective action recommendation is made.

3.7 Vent releases can occur through more than one unit at a time. Check unit vent monitors on all 3 units during a vent release.

. 4.0 Procedure 4.1 Meteorology Assessment 4.1.1 Record the following information on Enclosure 5.1.

Note:

The sources of data are listed in order of preference in the flowchart on Enclosure 5.1.

4.1.1.1 Unit(s) affected.

4.1.1.2 Date and time of reactor trip.

4.1.1.3 Report number.

4.1.1.4 Name of person preparing report.

4.1.1.5 Time Meteorological data taken.

4.1.1.6 Wind speed in miles per hour.

4.1.1.7 Direction from which the wind is blowing in degrees from North (North = 0).

4.1.1.8 Temperature gradient in degrees centigrade (AToC).

EDA-4 Page 4 of 11 2.24 (28,320 1 Ci

)(0.3 M~l/Ml )(63,330 -f&LZ ft 1E6 v mR/hr 120 sec where:

28,320 =

a conversion factor which converts cubic feet to milliliters 1ECi an activity conversion factor lE6iiCi 0.3 mR/hr=

a correlation value relating activity concentration to RIA's 16 and 17 response 63,330 ftn Steam volume released in a 2 minute (120 seconds) period. This is based on releasing 1.5E5 lbs of steam at 1050 psia with a 2 minute average steam release rate of 0.4222 ftn/lb-m.

2 =

The point at which the sum of RIA's 16 and 17 readings are averaged.

4.2.1.2 Record QNG on Enclosure 5.3.

4.2.1.3 Determine the iodine release rate, Q (Ci/sec),

by the following method:

I=

NG x Irat Where:

QNG Noble Gas Release Rate (Ci/sec) determined in Section 4.2.1.1.

I

= ratio of 1-131 equiv./Xe-133 equiv. from.6.

4.2.1.4 Record Q on Enclosure 5.3.

4.2.2 Containment Assessment (Enclosure 5.7) 4.2.2.1 Determine the noble gas release rate, QNG CA sec by one of the following methods; 4.2.2.1.1 Based on RIA 57/58 readings, as follows:

Q

= R/hr x CF Ci-hr x LR ml NG sec-ml-R/hr hr

EDA-4 Page 5 of 11 Where:

R/hr = RIA 57 or 58 reading in R/hr.

CF = Correction factor per Enclosure 5.8.

LR = Leak rate in ml/hr by one of the following methods:

based upon containment pressure, LR = Realistic Leak Rate, RLR,.9 (per Reference 2.10).

based upon an opening in (failure of) containment wall or penetration, LR = Opening In Containment, OIC, with supplied value being the diameter of the opening, Enclosure 5.9 (per Reference 2.11).

based upon design leakage rate, LR = 5.6E6 (per Reference 2.10).

4.2.2.1.2 Based on survey instrument, as follows:

Q

=R/hr x CF C-r-x LR a NG sec-ml-R/hr hr Where:

R/hr = survey instrument (PIC-6A) reading in R/hr.

CF = correction factor per Enclosure 5.8.

LR = Leak Rate in ml/hr as determined in Step 4.2.2.1.1 above.

4.2.2.1.3 Based on PAG sample as follows:

Q

= Conc. x 2.78E-10 x LR MI NG sec-UCi hr Where:

Conc. = the Xe-133 equiv. sample data (pCi/ml) from PAG sample.

2.78E-10 = units correction factor (1E -

6 Ci/pCi)(1 hr/3600 sec)

LR = Leak Rate in ml/hr as determined in Step 4.2.2.1.1 above.

EDA-4 Page 7 of 11 Where:

RIA = RIA reading in cpm or R/hr.

Use RIA-45 if reading < 1E7 cpm Use RIA-46 if RIA-45 is >

1E7 cpm and RIA-46 is < 1E7 cpm Use RIA-56 if both RIA-45 and 46 are > 1E7 cpm CF = correction factor per Enclosure 5.11.

CFM = unit vent flow rate in ft 3/minute.

4.2.3.1.2 Based on unit vent sample as follows:

QNG U-1 (Cone x 4.72E-4 X CFM) +

U-2 (Conc x 4.72E-4 x CFM) +

U-3 (Con x 4.72E-4 x CFM)

Where:

Conc. = the Xe-133 equiv. sample data in VCi/ml.

4.72E-4 Ci=

units correction factor sec-ft3 -Ci

.10.1 1 minute

.LIal 1E6pCi 60 seconds 3.5314E-5 ft2 CFM = unit vent flow rate ft3/minute 4.2.3.2 Record the noble gas release rate, QNG' on Enclosure 5.3.

4.2.3.3 Determine the iodine release rate, Q CL, by one of the following methods for I sec gh affected unit.

4.2.3.3.1 Based on QNG as follows:

I NG x Irat Where:

QNG = noble gas release rate determined in Section 4.2.3.1.

EDA-4 Page 8 of 11 Irat = ratio of 1-131 equiv./Xe-133 equiv.

from Enclosure 5.6.

4.2.3.3.2 Based on unit vent sample as follows:

Q, = U-1(Conc. x 4.72E-4 x CFM) +

U-2 (Conc. x 4.72E-4 x CFM) +

U-3 (Conc. x 4.72E-4 x CFM)

Where:

Conc. = 1-131 equiv. sample data in pCi/ml.

4.72E-4 = units conversion factor CFM = unit vent flow rate in ft2 /minute 4.2.3.4 Record iodine release rate, Q, on.3..

4.3 Dose Assessment (Enclosure 5.3) 4.3.1 Determine whole body dose due to noble gas as follows:

4.3.1.1 Determine the total noble gas release rate, TQNG' by adding QNG values from all source terms.

4.3.1.1.1 Record TQNG on Enclosure 5.3.

4.3.1.2 Determine the projected whole body dose in mrem,

DwB, for appropriate distances (1, 2, 5 and 10 miles unless specified otherwise) by:

NOIE:

DRWB on Enclosure 5.3 is the RWB hr whole body dose rate due to noble gas and is calculated for information or for use in other calculations.

DWB = TQNG x X/Q x 3.36E4 x 2 Where:

TQNG

= total noble gas release rate, determined in Step 4.3.1.1.

X/Q

= two-hour relative concentration value divided by wind speed, determined in Step 4.1.2.2.

3.36E4 = the adult whole body dose conversion factor in mrem-m' (per Reference 2.10).

hr-Ci

EDA-4 Page 10 of 11 4.3.3.3.2 Recommend a Site Area Emergency if the dose rate at the site boundary 50 whole body or a 250e thyroid (I-51 Equiv. _>

1.11E.-7 v9i1 1.

4.3.3.3.3 Recommend a General Emergency if the dose rate at the site boundary z 500OM whole body or > 2500ag thyroi r(I-131 equiv.

1.1E-6 he1/ml).

4.4 Determine if a release has been made using SLC Limits Release Status Case 1 -

Normal conditions No release Case 2 - Normal conditions plus Release within operating Limits event conditions are less Projected Dose as follows:

than or equal to SLC Limits Whole Body 5 1.01E-2 hr Reactor Building Pressure >

=ag 1 psig with increased Thyroid 5 1.71E-1 h activity OTSG Tube Leak Increased Vent Activity Field Team Activity 0

NOTE:

No dose projections are required for the counties/

state for Case 2.

Release Case 3 -

Normal conditions plus Projected Dose as follows:

event conditions are Whole Body > 1.01E-2 M =

greater than SLC Limits hr Thyroid > 1.71E-1w hr 5.0 Enclosures 5.1 Oconee Meteorology, 1 Page, 10/91 5.2 Oconee Two-Hour Relative Concentration Factors (CH), 1 Page. 10/91 5.3 Oconee Dose Assessment Report For Emergency Notification 2 Pages. 10/91 5.4 Oconee Protective Action Zones Determinations, 2 Pages, 10/91 5.5 Oconee Source Term Assessment-Steam Relief Valves, 1 Page, 10/91 5.6 Oconee 1-131 Equivalent/Xe-133 Equivalent Ratio. 1 Page, 10/91 5.7 Oconee Source Term Assessment-Containment, 1 Page, 10/91

EDA-4 Page 11 of 11 5.8 Oconee Containment Noble Gas Correction Factor. 1 Page, 10/91 5.9 Oconee Containment Leakage Rate, 1 Page, 10/91 5.10 Oconee Source Term Assessment-Unit Vent, 1 Page, 10/91 5.11 Oconee Unit Vent Noble Gas Correction Factor, 1 Page, 10/91

Enclosure PagelI of

[ f0' 10-91 OCONEE TWO-HOUR RELATIVE CONCENTRATION FACTORS (CH)

EDA-4 Temperature Stability, Distance (Mies)

Difference Class AToC 1

2 3

4 5

6 8

9 10 I

)

g I

I I

Ig I

I l

l

< -0.95 A

l1.8E-6 6.2E-7 4.3E-7 3.4E-7 2.8E-7 2.4E-7 2.1E-7

.8E-7 1.7E-7 1.5E-7 I

I I

IIII III I

I III IIIIII I

I I

I I

I I

I I

IIII

-0.95 to -0.86 f B

1.

7E-5 4.2E-6 1.9E-6 1,1E-6 J6.7E-7 I4.7E-7

3. 5E-7 :2.7E-7 I2. 1E-7
1.

7E-7 I

I II II I

III I

I II III II

-0.85 to -0.76 C

4.6E-5 1.4E-5 6.4E-6 3.8E-6 2.69-6 1.8E-6 1.4E-6 1.1E-6 8.8E-7 7.4E-7 IIII II I

I I

IIIII IPII I

I I

IIII IIII I

I I

II I

.I

-0.75 to -0.26 D

1.2E-4 l 5.2E-5 2.9E-5 1.8E-5 1.4E-5 1.OE-5 8.OE-6 6.7E-6 5.7E-6 4.9E-6 I

I IIIIII II III IIg I

I II II I

I II IIIII

.25 to +0.74 E

l 2.7E-4 1.OE-4 5.9E-5

-5 1.6E I

I I

I I

I I

I I

I I)

+0.75 to +2.0 F

5.3E-4 2.3E-4.3E-5 5.8E-5 4.7E-5 4.OE-5 3.4E-3.OE-5 I

I I

G 8

4 2

I 1

1 I

8 I

I I

II II III I

I I

II III I

J I

III I

.I

> 20l G

l8.8E-4 4.SE-4 I29-

.E4 15-

.2-

.O-

.8-

.5-

.6 IIIIIII I

I II I

IIIII

4.

l 4.3E-7 3.4E-7

.3 Page 1 of 2.

10-91 OCONEE DOSE ASSESSMENT REPORT FOR EMERGENCY NOTIFICATION EDA-4 W

rt Date/Time:

Reviewed by:

1.

THIS IS A DRILL THIS IS AN ACTUAL EMERGENCY NUMBER 9 EMERGENCY INVOLVES:

Release above normal operating limits Release below normal operating limits (no projected dose required)

A NO RELEASE (IF A. go to item 14.)

CA RELEASE IS OCCURRING: Started Epected Duration B POTENTIAL RELEASE D A RELEASE HAS OCCURRED: Started Stopped

10. TYPE OF RELEASE: 0 Ground Level A RADIOACTIVE GASES C RADIOACTIVE PARTICULATES B RADIOACTIVE LIQUIDS D OTHER
11.

RELEASE:

0 CURIES PER SEC.

Sta Relief Contain.

Vent Total Ci/sec NOBLE GASES Q ---

4 GC-QNG......-

NGN Stm Relief ontan.

Vent Total Cilsec IODINES Q

+ Q

+ p v_

'I 8 IODINE/NOBLE GAS RATIO (If available)

D OTHER

13. ESTIMATES OF PROJECTED OFFSITE DOSE:

0 NEW o UNCHANGED DURATION:

HRS.

Whole Body mrem Mile NGCH x 3.36E4 DRWB hr x

2 D,,mrem Wind Speed 3.36E4 3.36E4 3.36E4

,-L3.36E4

.4 Page 1 of 2.

10-91 OCONEE PROTECTIVE ACTION ZONES DETERMINATION EDA-4

1.

Determine PAZ by completing one of the options under A or B, using meteorological data from Enclosure 5.1. Record the PAZ on Enclosure 5.3.

A.

Daytime (1000-1600 hrs.)

1)

Wind speed > 5 mph for tower or river wind direction; use the table below.

2)

Wind speed < 5 mph for tower or river wind direction. Assume Sectors AO, Al, Bl, Cl, D1, El, and Fl are affected. Then use the table below to determine additional PAZ.

3)

For NWS wind direction. Assume all sectors are affected (AO.

Al through Fl, A2 through F2).

B.

Nighttime (1600-1000 hrs.)

(If river wind direction is unavailable, assume 700-210.)

1)

If river wind direction is between 210*-70*, use Option A (Daytime).

2)

If river wind direction is between 700-2100, assume all sectors are affected (AO, Al through Fl, A2 through F2).

WindDirectin Protective Action Zones 14.1 -27*

AO, Cl, C2, Dl, D2, El, E2 27.1-420 AO, Cl, D1, D2, El, E2 42.1.-660 AO, DI, D2, El, E2 66.10-850 AO. Dl, D2, El, E2, F2 85.1*-1040 AO, Dl, D2, El, E2, Fl, F2 104.10_129*

AO, El. E2, Fl, F2 129.10-1560 AO, Al, A2, El, E2, Fl, F2 156.10-1750 AO, Al. A2, El, Fl, F2 175.10-181 AO, Al, A2, Fl, F2 3.81.10-2190 AO, Al. A2, Bl, B2, Fl. F2 219.10-2550 AO, Al, A2, Bl, BZ 255.1-2710 AO, Al, A2, Bl, B2, Cl, C2 271.10-2970

.AO. BI, B2, Cl, C2 297.10-3120 AO, 3l, B2, Cl, C2, D2 312.10-3450 AO.

Bl, B2, C1, C2, D1, D2 345.10-14*

AO, Cl.

C2.

Dl, D2

.4 Page 2 of 2 10-91 OCONEE PROTECTIVE ACTION ZONES DETERMINATION EDA-4 2.*

Submit protective action guides to the Offsite Radiological Coordinator based on the calculated dose from Enclosure 5.3 and the following information.

A)

Recommend Evacuation of Population in affected area. For doses:

>.5 Rem Whole Body or,

> 25 Rem Thyroid B)

Recommend evacuation of children and pregnant women, and sheltering of remainder of personnel in the affected area. For doses:

1-5 Rem Whole Body or, 5-25 Rem Thyroid C)

Recommend no action. For doses.

< 1 Rem Whole Body or,

< 5 Rem Thyroid

  • NOTE:

For all evacuations, recommend that the remainder of the 10 mile emergency planning zone remain indoors.

.6 Page 1 of 1 10-91 OCONEE 1-131 EQUIVALENT/Xe-133 EQUIVALENT RATIO EDA-4 Time Since Ratio Based Ratio Based On Trio Chrs)

On LOCA.(Column 1)

Core H-elt (Column 2) 0 4.83E-3 2.24E-3 2

6.16E-3 1.06E-2 4

7.09E-3 1.56E-2 8

8.31E-3 2.79E-2 24 9.76E-3 7.40E-2 48 1.02E-2 1.10E-1 100 1.09E-2 1.34E-1 250 1.43E-2 1.79E-1 500 2.26E-2 2.90E-1 720 3.32E-2 4.31E-1 NOTE:

A)

For I releases in which Irat is utilized to determine 1-131 equiv.

concentration, apply the appropriate correction from the table below.

Ratios are per Reference 2.10.

1. LOCA, use column 1 (BASED ON LOCA.
2. LOCA throurhcharcoal filters, divide column 1 value by 100.
3. Core dam-ae, use column 2 (BASED ON CORE MELT).
4. Core damage throueh charcoal filters, divide column 2 value by 100.
5. Tube rupture, use 3.32E-5.
6. ew fuel accident, use 2.23E-4.
7. Old fuel accident, use 7.18E-4.
8. Gas decay tank, assume no radioiodine released, only noble gases are considered to be released from gas tank.

B)

For j jam RaleAE YaLve releases in which Irat is utilized to determine 1-131 eq concentration, apply the appropriate correca tion from the table below. Ratios are per Reference 2.10.

1. LOCA, divide Column 1 values by 100.
2. Core Melt, divide Column 2 valves by 100-

.7 Page 1 of 1 10-91 OCONEE SOURCE TERM ASSESSMENT-CONTAINMENT EDA-4 Unit(s) 12 Report #

(circle one)

Reactor Trip

/

Projection based on data on _

date time date time Calculations based on:

Core Melt/LOCA (circle one)

Containment pressure psig LR =

ml/hr LR based on (check one):

Realistic Leak.Rate (Encl. 5.9)

.__-Opening in Containment (Encl. 5.9) (circle one) 1" 2" 4" 6" 8" 12" 18" 48" Diameter opening Design Leak Rate.(5.6E6)

Based on RIA-57 and 58 RIA

-Cl-hr (or PIC-6A) 8_

X CF see-ml-R/hr X LR hr =Q see Reading hr (Encl. 5.8)

X X=

Based on FAG sample Conc.

m" x

2.78E-10 ci-hr m1 OA Ml see-UCi x LR hr =

QNG sec x

2.78E-10 x

=

Iodin Based on Irat CCi QNG sec x Irat (Encl. 5.6) =Q see x=

Based on PAG sample Conc. aI&

x 2.78E-10 Ci-hx M_

ml sec-uCi x LR hr

=

sec x

2.7 8-10 x

_=

Prepared By:

.9 Page 1 of 1 10-91 OCONEE CONTAINMENT LEAKAGE RATE EDA-4 Leak Rate versus Pressure (RLR)*

Pressure Leakage Rate losial

(-ml/hr) 1 1.00E5 5

4.734E5 10 9.693E5 15 1.443E6 20 1.916E6 25 2.389E6 30 2.885E6 35 3.314E6 37 3.471E6 40 3.652E6 42 3.764E6 45 3.922E6 47 4.012E6 50 4.103E6 52 4.148E6 55 4.193E6 57 4.21SE6 59 4.238E6

  • NOTE:

(Per Reference 2.10)

Leak Rate Yersus Size Qpening 1Q)**

Opening Diameter.(inches)

Actual ftn/hr Actual ml/bx 1

15,100 4.276E8 2

60,400 1.710E9 4

241,600 6.842E9 6

543,500 1.540E10 8

966,200 2.737E10 12 2,174,000 6.158E10 18 4,892.000 1.386E11 48 34,785.000 9.853E11

  • r*Note:

(Per Reference 2.11)

1)

For all pressure greater than 30 psia and temperature greater than 280*F (conservative for lower temperatures or pressures).

2)

Leak rates for 12 inches and larger are more than one reactor building volume per hour. In an accident, these leak rates could not exist for more than a few minutes.

3)

Size opening is diameter of the opening.

.10 Page 1 of 1 10-91 OCONEE SOURCE TERM ASSESSMENT-UNIT VENT EDA-4 Unit(s)

-2 Report #

Reactor Trip

/

Projections based on:

f date / time date / time Calculations on: Core Melt/LQCA (circle one)

Noble Gas; Based on o45 g46 056 Appropriate Vent QNG Total RIA 45, 46 or 56 Correction Factor X Flow

=

NG s (add U-1,23) cpm or R/hr value (Enclosure 5.11)

CFM U-1) x U-2)

X U-3)

X Vent Sample C

Vent gL Activity =21 X

4.72E-4 sec-ftn-lICi X

Flow

QNG see ml CFM SX 4.J2E-4 X

Based on I/Xe ratio QNG Total see X

Irat (End. 5.6) =

0 sec Based onA nit Vent Sample Vent Sample Ci-minal Vent gi Activity Mgq X

4.72E-4 sec-ftn-vCi X

Flow

=

sec ml CFM X

U.:-

x__

Prepared By:

II

Enc los*.

Page 1*

10-91 OCONEE UNIT VENT NOBLE GAS CORRECTION FACTOR*

EDA-4 Time Since RIA-45 RIA-46 RIA-56 Other rip (h.)

Core Melt Core Melt Core Melt Accidents LOCA 0

8.874E-11 1.647E-08 1.472E-03 LOCA thru Filter Tube Rupture 2

1.261E-10 6.183E-08 6.651E-04 Old Fuel Gas Tank 4

1.133E-10 2.072E-07 5.990E-04 RIA-45 Use 2.164E-11 8

8.336E-11 2.837E-07 4.358E-04 24 4.446E-11 2.025E-07 2.476E-04 RIA-46 use 1.605E-7 48 3.450E-11 1.732E-07 2.113E-04 RIA-56 use L.340E-4 100 3.144E-11 1.628E-07 2.071E-04 250 3.162E-11 1.605E-07 L.943E-04 New Fuel 500 2.860E-11 1.581E-07 1.613E-04 RIA-45 use 3.144E-11 720 2.164E-11 1.605E-07 1.340E-04 RIA-46 use 1.628E-7 Units in Ci-min/sec-ft3 -cpm.

or Ci-min/sec-ft3-R/hr RIA-56 use 2.071E-4

  • Correction factors per Reference 2.10 x 2.832E4 mi/ft2 x I min/60 sec x 1m3/1E6 ml
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