ML20053E435

Public Version of Revision 3 to Emergency Plan Implementing Procedure 1004.7, Offsite/Onsite Dose Projections.

ML20053E435
Person / Time
Site:	Three Mile Island
Issue date:	05/07/1982
From:	Nelson M, Toole R GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20053E430	List: ML20053E433 ML20053E435
References
0047W, 1004.7-01, 1004.7-1, 47W, NUDOCS 8206080050
Download: ML20053E435 (20)

Text

'

FOR.USE lN ONIT 1 ONLY 1004.7 Revision 3

- 05/07/82 IMPORTANT TO SAFETY NON-ENVIRONMENTAL IMPACT RELATED CONTROLLED COPY FOR THREE MILE ISLAND NUCLEAR STATION USE IN UNIT I ONLY UNIT NO. 1 EMERGENCY PLAN IMPLEMENTING PROCEDURE 1004.7 0FFSITE/0NSITE DOSE PROJECTIONS ff ,

Table of Effective Pages Page RevisforL Page Revision Page Revision Page Revision 1.0 3 2.0 3 3.0 3 4.0 3 5.0 3 6.0 3 7.0 3 8.0 3 9.0 3 10.0 3 11.0 3 12.0 3 13.0 3 14.0 3 15.0 3 16.0 3 .

17.0 3 18.0 3 19.0 3 (Petc) 0

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51'gnature nu (b"/2 Dite F]- 8Z, Signature Date Document ID: 0047W D AbOOK0 0 89 F PDR FOR USE IN UNIT i ONLY

FOR USE lN UNIT I ONLY 1004.7 Revision 3 05/07/82 i

'OV IMPORTANT TO SAFETY I NON-ENVIRONMENTAL IMPACT RELATED CONTROLLED COPY FOR I THREE MILE ISLAND NUCLEAR STATION UNIT NO.1 EMERGENCY PLAN IMPLEMENTING PROCEDURE 1004.7 0FFSITE/0NSITE DOSE PROJECTIONS ,

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Table of Effective Pages .

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!oo8L Signature 5=7- 8t Date Document ID: 0047W FOR USE IN UNIT I ONLY

i FOR USE IN UNIT 1 ONLY 1gg4,,

l Revision 3 r

q THREE MILE ISLAND NUCLEAR STATION V UNIT NO.1 EMERGENCY PLAN IMPLEMENTING PROCEDURE 1004.7 ,

0FFSITE/0NSITE DOSE PROJECTIONS j 1

1.0 PURPOSE ,

l The purpose of the procedure is to provide.

a. Techniques and methods for calculating projected doses (whole body, and tityroid dose equivalent which might result from monitored releases of radioactive materials from TMI Unit 1.

b. Techniques and methods for predicting the downstream concentrations of radioactive liquids resulting from a major accidental release of radioactive liquids to the Susquehanna Valley.

c. Contingency methods for estimating projected doses if monitors are oit of service or off-scale high.

l The Radiological Assessment Coordinator is responsible for imple-1 O mentina this Procedure.

! 2.0 ATTACHIENTS 2.1 Attachment I Dose Assessment Sheet 2.2 Attacinent II Meteorological Data 2.3 Attachment III Calculation of the Source Tera and Onsite/Offsite Dose Projections 2.4 Attacirnent IV Contingency Calculations 2.5 Attachment V Liquid Release Calculatio1 2.6 Attachment VI Protective Action Guides 2.7 Attachment VII Field Monitoring Nomograph

3. 0 EMERGENCY ACTION LEVELS l

3.1 As required by an Emergency Plan Implementing Procedure.

3.2 As directed by the Emergency Director or his designee.

'O 1 1

1.0 l FOR USE IN UNIi 1 ONLY l

1004.7 FOR USE IN L} NIT I ONLY Revision 3 4.0 EMERGENCY ACTIONS O'-- INITIALS

NOTE: Perform steps in order:  :

If the release is radioactive materials to the  :

atmosphere, perform Steps 4.1 - 4.5.  :

If release is of radioactive liquids to the  :

Susquehanna River perform Steps 4.F - 4.8.  :

4.1 Complete the Meteorological section of the Dose Assessment Sheet by completing Attachment II.

4.2 Complete the Release section, Source Term and Dose Projection section of the Dose Assessment Sheet by completing forms on Attachment III.

_4. 3 Utilize Attachments VI and VII to evaluate Field Monitoring data and recommend Protective Action.

4.4 Utilize Attachment IV to project dose based upon contingency calculations.

4.5 Always report dose rate, dose, time used, and basis for the time estimate to the Emergency Director, or his designee.

4.6 Compile the expected downstream concentrations by performing the steps and completing the forms in Attachment V.

4.7 Compile the time for the flume to reach downstream users and a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> average concentration by completing the remaining steps in Attachment V.

4.8 Report results to the Emergency Director or his designee.

i 2.0 FOR USE IN UNIT l ONLY

FOR ~USE IN UNIT I ONLY 100,,,

Revision 3 ATTACHMENT I DOSE ASSESS >ENT SHEET 1.0_ Meteorological Section 1.1 Time 1.4 Pasquil Stability Class 1.2 Date _

=1.3 Wind Direction 2.0 Release Section 2.1 Release Pathway 2.2 Monitor Designation 3.0 Soun:e Tenn Calculation 10-6 x Meter Reading x lleter Conversion x Ventilation = Source Factor Flowrate Tenn l  :  :  :

uci /

/ cpm or cpm min j

[ cc }  :

fcc )

l Ci\

(secj g

c  : (sec j

k pm or cpm) min  :  :

O  :

Noble Gas $ $ =

Channel  :  :  :

l  :  :  :

Radiofodine x x =

Channel 1

l l

l O ~i 3.0 FOR USE IN UNIT l ONLY i

~

O 0 1004.7 R3 vision 3 O~ -

Tl 4.0 Onsite/Offsite Dose Projections O-D Source x Dispersion x 1 mph x Dose x Estimated = Dose C Te rm Factor Wind Speed Conve rsion Du ration (f)

Facto r g

, "T1  :  :  :  :  :

! O ,/ ci l :

rSec)  :

/ mph)  :

( mrembour)

( ho"rs)  : = mrem

2

y (secj

(

(m3 /

l

(mP]h  :

C1  :  :

3

(- .

. ( -

) . .

[

:  : m3  :  :

i- (O  :  :  :  :  :

7 i

ITl Noble Cas x x x 4E5 x =

q Channel  :  :  :  :

i Z  :

~

i Radiciodine  :  :  :  :  :

C Channel x x x 6E8 x =

Z '

Z r-9 4 l -

l O . . .

Z

Dose i Di stance  ;

i F  :  :  :  :  :  :  :  :

i] f  : (mrem) 200m  :

400m  :

EA  :

2LPZ  :

SEPZ  :

10EPZ  :

i

}  : Whole Body  :  :  :  :  :  :  :

1 -:  :  :  :  :  :  :  : ,

j  :  :  :  :  :  :  :  :  !

j  : Thy ruid  :  :  :  :  :  :  :

i  :  :  :  :  :  :  :  : .

i l

t

}

j 4.0 i <

_ __ m - _ _ _ _ _ _ _ _

FOR USE IN UNIT 1 ONLY so4;l,,3 ATTACINENT II METEOROLOGICAL DATA  :

1. Reco M the following infonnation on tie [bse Assessment Steet in the Meteo rological section.

1.1 Time of Day 1.2 Date 1.3 Wind Di rection (pe r RecoMe r WDS-1A in degrees radian) )

1.4 Pasquil Stability Class (pe r the algo rittra desc ribed below)

Is the diffe rential tempe rature (dt) available?

(Reco Me r WDS-1A )

Ye s No Is tte wind range available?

(Reco Me r WDS-1A )

Is the dt > -0.3 77 Ye s No Ye s No Stable i Class F Is the wind range < 45 7

(^ Stable Class F Stable Ye s No Class F I

Is the wind range > 75 4 Ye s No Is the dt < -1.0 77 Ye s No Unstable Neutral Class B Class D Unstable Neutral Class B Class D O

5.0 l

l FOR USE IN UNIT I ONLY

FOR USE IN UNIT 1 ONLY 1004.7 Revision 3

2. Detemine the dispersion factors that correspond to the correct stability class l

from Table 1, Dispersion Factors. Record the dispersion factors on the Dose l Assessment Sheet, in the Onsite/0ffsite Dose Projection section.

l I

Table 1, Dispersion Factors Pasquil Stability : Distance Class  : 200m : 400m  : EA  : 2LPZ  : SEPZ  : 10EPZ B  : 7.7 E-4 : 2.75 E-4 : 1.1 E-4 : 2.2 E-6 : 7.4 E-7 : 4.7 E-9 D  : 3.8 E-3 : 1.35 E-3 : 5.4 E-4 : 5.1 E-5 : 1.3 E-5 : 5.2 E-6 F  : 9.1 E-3 : 3.25 E-3 : 1.3 E-3 : 2.0 E-4 : 7.0 E-5 : 3.2 E-5 Record the Wind Speed (per recorder WDS-1A in mph) on the Dose Assessment Sheet in the Onsite/Offsite Dose Projection section.

i l

l O

i FOR USE lb UNIT I ONLY

l FOR USE IN UNIT 1 ONLY 100,,,

Revision 3 ATTACHMENT III Calculation of the Source Tenn and Onsite/0ffsite Dose Prtjections

1. Identify t.he affected atmospheric radiation monitor (s) per the Radiation Monitorf ng System (RMS) Schematic by comparing the " actual" indicated

, concentration of radionuclide to the " normal observed" level. If more than one monitor on a Release Pathway is affected then choose the monitor furthest downstmam of the release sourte. If all monitors in a Release Pathway are out-of-service or off-scale then proceed to the Contingency Calculations, Attachment IV.

Record the monitor designation and Release Pathway on the Dose Assessment Sheet, in the Release section.

2. Record the Noble Gas Channel and Radiofodine Channel readings for the affected monitor on the Dose Assessment Sheet in the Source Tenn Calcula-tion section.

3. Record on the Dose Assessment Sheet in the Source Tena Calculation section, the Meter Conversion Factors that cormspond to the affected I

monitor. The Meter Conversion Factors are listed on Table pmsented below:

Table 2 Meter Conversion Factors

'O Monitor Designation :

Meter Conversion Fectors uci

Noble Gas [ uci cc ):: Radioiodine [ cc }

I

cpm cpm

k ):: ( mi n /

RM-A2  : 2.52 E-08  : 8.33 E-1D RM-A4  :  :

RM-A5  :  : N/A RM-A6  :  : 8.33 E-10 RM-A8  : 2.7 E-08  : 7.7 E-10 RM-A9  : 2.56 E-08  : 7.2 E-10 l

: I

7. 0 l FOR USE IN UNIT I ONLY

R)DiEMATIC DRMING Q i

. STAT 1oM VENT 9

33 M'A6% 4 RM-A9 f24000cfM) (/)

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AdKILIAer'8UILDIAQ RM-A4 3 $0'00**#'**" gancipgawsta% /u Ucf (p, con cpm)

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L ' tFOR USE INzUNO 1 ONLY 100,,,

Revision 3

4. Deternine the Ventilation Flowrate for the affected Release Pathwy.

$ TABLE 3 YENTILATION FLOWRATE

. )

i, Release Pathway  : Ventilation Flowrate 1

Recorder

1. Station Vent (RM-A8)  : 1. FR-151 (CFM)

2. Auxiliary Building  : 2. FR-150 (RM- A6)  :

l 3.- Fuel Handling Building  : 3. FR-149 (RM-A4 )  :

4. Reactor Building Purge  : 4. FR-148 (RM-A9)  :

Multiply the Ventilation Flowrate in (CFM) by 472 to obtain the ventilation Flowrate in (cc )

sec .

Record on the Dose Assessment Sheet in the Source Tenn Calculation section  ;

dia ventilation flowrate.

5. Calculate the Sourt:e Tenn (Ci ) as indicated by the Dose Assessment sec Sheet, Attachment I.

i

6. Calculate the Onsite/0ffsite Dose Projections as indicated by the Dose Assessment Sheet, Attachment I.

7. Detennine the Emergency Action Level (EAL) utilizing Table 3 and the l

l Exclusion Area Dose Projection.

l O l l 9. 0 FOR USE IN UNIT I ONLY

y FOR USE IN LINIT 1 ONLY ^ 1004.7 Revision 3 4

TABLE 3 EMERGENCY ACTION. LEVELS (EAL) l

~

l EAL  : Fraction of Lower Limit : Whole Body' , '

l

Protective Action Guide : Gamma Exposure )

at Site Boundary (EA)

Al ert  : .01,  : > 10 urem < 50 mrem +

f.

hour hour s

i  : a Site Emergency  : .05  : -

> 50 mmm d 1 Rem

.  : hour i . hT

: ~

General Emergency : 1  : .. ) 1 Rem /hr. ' '

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d FOR OSE IN L} NIT 1 ONLY 1004.7 Revision 3 ATTACHENT IV O Contingency Calculations

1. Utikize Table 1 if the radiation monitors nonna11y used to monitor the containment and/or other plant effluent paths are out of service or off-scale high. The Emergency Director shall select a classification from (1-V). Ccmputations shall be made using the Source Terms identified in Table 1. Transfer the noted Source Tenns to the Dose Assessment Sheet, Attachment 1.

2. RM'-G8 meter readings, containment pressure indications and Table 2 shall

, be utilized in lieu of Table 1 (Case I and II) Source Terms when

~possible. Transfer the Source Term computed utilizing Table 2 to the Dose Assessment Sheet, Attachment 1.

n

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o k

g 6

O 11.0 FOR USE IN UNIT I ONLY

FOR USE IN L} NIT I ONLY 1004.7 Revision 3 Contingency Calculations Table 1 Classification  : Source Tenn [Ci j

(sec/ ,

Case I LOCA  : Whole Body  :' T hy roid

1. Fuel Melting  :  :

2. No Com Cooling  : 1.0  : 1.5 E-1

3. 100% Noble gases and 25%  :  :

iodines in the core released to :  :

contairunent  :  :

4. Contairunent Maximum Design Leak :  :

Rate  :  :

5. FSAR 14.2.2.4  :  :

Case II LOCA  :  :

1. No Fuel Melting  : 6.5 E-2  : 1.5 E-3

2. TFm cooling maintained  :  :

3. 100% GAP release  :  :

4. Containment Maximum Design Leak :  :

Rate  :  :

5. FSAR 14.2.2.3  :  :

Case III  :  :

Case Decay Tank Ruptum  : 25  : 4.4 E-3

1. Total contents of tank mieased  :  :

90,000 Ci Noble Gas,  :  :

16 Ci D.E. 1-131  :  :

C 2.

case IV FSAR 14.2.2.5  :

Fuel Handling Accident  : 4.7  : 1.5 E-4

1. Reactor is S/D for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />  :  :

2. 56 Fuel mds suffer mechanical  :  :

damage to the cladding with GAP  :  : 2 mlease.  :  :

3. 100% Noble Gas and 1% of the  :  :

iodine is mieased to Fuel  :  :

Handling Guilding Atmosphem  :  :

4. Charcoal filters on FIE ventil-  :  :

ation system absorb 90% of the  :  :

iodine.  :  :

5. FSAR, 14.2.2.1  :  :

case v  :  :

Steam Generator Tube Ruptum  : 1.0  : 9.3 E-4

1. Double-ended mptum of one S/G  :  :

tube  :  :

2. Radioactivity is mieased thmugh:  :

the turbine bypass to the con-  :  :

denser and then out the conden-  :  :

sate vacuum pump exhaust.  :  :

3. The gas to liquid partitign  :  :

factor for iodines is 10-  :  :

O 12.0 FOR USE IN UNIT I ONLY

1004.7 Revision 3 d i C0f0NGfNCV t CMCAMTIQ)is TABLE 2 F0.R USE IIN v6N, i i v.vui REACTOR BUILDING UNCORRECTED RM-G8 SOURCE TERM NOMOGRAPH REACTOR BUILDING D READING d (mR/hr)

SOURCE TERM (Ci/sec) is so' _ a,p l*7 l Align the uncormeted RM-G8 mading nr1 with the  :

. Tr/  :

reactor building pmssure (psig). The intersection El 3

point of this line with the vertical right hand scale is the mactor building source tem /Cl .

g secj 5 4

l E i REACTOR BUILDING g,s 1 PRESSURE E (psig) $

i ne' l}g2

tro

1 _

. . .u -

S . . s.o yz (q 4

< to @

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=3 l2 1 18 E tso a E 3+

i: Es

=

t 1 56 f E7 j Assumptions: 38 1 i u,5

' 1. Reactor building f me volume (2E6 f t3 )

li q i v io

-e l' 2. Reactor building source tem  :

l',' 9E*4 Noble gas l 94 Radioiodines 3

3. Containment leakrate a function of containment 51

l. pmssum. g 5

3 53 I s+

n.

i

$2 g,5 5.6 13.0 h$

i me* y n -

u =

=

p FOR USE IN UNIT l ONLY 5

"' 3

FOR USE IN UNIT 1 ONLY g4g,,3 ATTACHIENT V LIQUID RELEASE CALCULATION

1. Estimate quantity of radioactive liquid released or the release rate of the liquid being released gallons or gpm.

Lla) (Ib)

2. From recorded infonnation or sample analysis detennine the activity level (in uCi/ml) of the released liquid: pC1/ml.

(2)

3. Obtain the river level by calling the River Forecast Center in Harrisburg at phone number 782-2256 or 782-3488 and record the reading: f t.

(3)

4. Find the river flow corresponding to the river level No. 3 above, in Attachment II, and record: CFS.

(4)

5. Calculate the average and maximum downstream concentrations of radio-(]

active material as follows:

Maximum uCi 3 cfs uCi**

ml x gpm x 2.33 x 10 gpm + cfs = ml W (Ib) (4) DIT-

NOTE: ** If the average or maximum downstream concentration  :

$ is > 1 x 10-6 pCi/m1, notify downstream users to

curtail intake.  :

14.0 FOR USE IN UNIT 1 ONLY

~

FOR USE IN UNIT i ONLY g,yg,, 3 ATTACHENT V Time for Flume to Reach Downstmam Users

6. Downstmam Points ( Appendix XII)

7. Distance tc Point in miles

( Appendix XII)

(9) W (9)- (9) (9)

8. River velocity in moh cor-TTOT TIDT TIDT (10) TIDT msponding to river flow from (4) above (Table 1)

9. Calculate a time in hours for the flume to mach selected point: Step 7 Step 8 24 Hour Average Concentration in Unrestricted Areas

10. Record the duration of the release in minutes: min.

11. Calculate a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> average concentration in unmstricted amas:

pCi _4 pCi ml x min x 6.9 5 x 10 = ml

" TEAT (1) (1)

O

• 15.0 FOR USE IN UNIT I ONLY

FOR USE IN UNIT 1 ONLY 1004,7 Revision 3 ATTACHMENT V U-

12. Determine the estimated fraction of MPC:*

uCi ml + MPC** = Fraction of MPC W w W

NOTE:

• If the ratio obtained in (14) of Attachment is >500, :

notification of NRC is required with 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per  :

10CFR20.403. If the ratio obtained in >5,000,  :

immediate notification is required per IOCFR20.403.  :

NOTE: ** MPCw is the weighted MPC for the isotopes released.  :

$ If unknown, use 3 x 10-8 pC1/ml. $

O 16.0 FOR USE IN UNIT I ONLY

FOR USE IN UNIT 1 ONLY g;7 ,, 3 ATTACHMENT V c'~

TABLE I RIVER FLOW VS. RIVER LEVEL A B C D Gauge Reading River Elevation Market Street at TMI River Flow River Bridge, Hbg. (Feet Above (Cubic Feet Velocity (Feet) Sea Level) per Second) (MPH) 4.3 278.7 20,000 .9 5.3 279.5 40,000 1.4 6.2 280.1 60,000 .7 7.1 280.7 80,000 2.0 8.1 281.3 100,000 2.3 10.4 282.5 . 150,000 2.6 12.5 283.6 200,000 3.1 14.3 284.9 250,000 3.3 16.1 285.8 300,000 3.5

~1 17.9 (d 19.5 287.0 288.1 350,000 400,000 3.7 3.9 21.2 289.7 450,000 4.1 22.7 291.0 500,000 4.3 24.3 292.6 550,000 4.5 25.6 294.0 600,000 4.7 26.9 295.2 650,000 4.9 28.1 296.1 700,000 5.1 29.3 297.1 750,000 5.3 30.4 298.1 800,000 5.5 31.3 299.2 850,000 5.7 32.0 300.1 900,000 5.9 32.6 301.1 950,000 6.1 33.1 302.0 1,000,000 6.3

NOTE: River elevations 302.0 feet at water intake struc-  :

ture TMI requires initiation of EPIP 1004.2 ALERT.  :

17.0 FOR USE IN UNIT I ONLY

FOR USE IN UNIT 1 ONLY 1004.7 Revision 3 ATTACHl(NT VI Protective Action Guides Emergency Action  : Actual or Projected Exclusion Level (EAL)  : Area Dose (mrem)

Whole Body  : Thyroid

1. Unusual Event  : <10  : <50

2. Alert  : >10 <50  : 150 <250

3. Site Emergency  : >50 <1000  : >250 <5000

4. General Emergency  : > 1000  : >5000 Protective Action  : Actual or Projected Exclusion Guide (PAG'S)  : Area Dose (mrem)

O l Whole Body  : Thyroid Lower Limit (PAG)  : 1  : 5 Upper Limit (PAG)  : 5  : 25 i O 18.0 FOR USE IN UNIT I ONLY r

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

FO.R tJSE IN LINITATbOMLvli

. AIRBORNE 10 DINE SAMPLE NOMOGRAPH Note: This nomograph is to be used for Iodine 131 vfson3 C M- kg. CPM) air samples counted with a SAM 11. ihis nomograph gg c assumes an ave. counter factor of 7800 for SAM ll's.

B 131 T

Airborne Activity Ai*

20. (y 3) Sat:: ole Volume(tr.1 c: cc) (uCi/r11 p z.-5 8

. - 7 G

4 0,,,, .II3 - 5

-2I3 -

4

'1 70~ .

14E3

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1 7. 5:- 2E5 .- 4 10 g 700,,,' .

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- 1 E6 40 '.:

~ 2E*

2000 100. -

_i 7,7

-8

-a 4 C:: ,,, -t

-5

-4

.,000 Instructions: Draw a line through Net CPM (A) and Air Sam ~3

'. and read 11 ge Airborne Volume (B) using (C)

Activity a straight on theedge line.

1 ~..,,, .

-1 2000D _ -I E-B

-1

-8

-7

-6 40000 .

-5

-4 coo _ _

-3 100000 J ,

-1 FOR USE IN UNIT I ONLY t _ -- _ - - __ ____- - _ --- - -_ _ _ _ 3 E- o