ML20062K735

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Public Version of Revision 4 to Emergency Plan Procedure 1004.7, Offsite/Onsite Dose Projections
ML20062K735
Person / Time
Site: Three Mile Island Constellation icon.png
Issue date: 07/30/1982
From: Nelson M, Toole R
GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20062K726 List:
References
0047W, 1004.7-01, 1004.7-1, 47W, NUDOCS 8208170359
Download: ML20062K735 (24)
v • d • e


Text

_ _ _ . _ _ _ -- .

_ . _ . . _._. _ _ . _;_ r

' FOR 'JSE IN UNIT 1 ONLY 1004.7 Revision 4 07/30/82 e

O k- IMPORTANT TO SAFETY CONTROLLED COPY Fan 1 NON-ENVIRONMENTAL IMPACT RELATED USE IN UNIT 19 SLY,

_ - THREE MILE ISLAND NUCLEAR STATION UNJT NO.1 EMERGENCY PLAN IMPLEMENTING PROCEDURE 1004.7 0FFSITE/0NSITE DOSE PROJECTIONS o/v% 6 x.S s

' ' Table of Effective Pages Page Revision Page Revision Page Revision Page Revision

~ 1.0 4 2.0 4 3.0 3 4.0 4 5.0 4 6.0 4 7.0 3 .

8.0 3 9.0 3 ,

10.0 3 11.0 3 12.0 3 13.0 3

, 14.0 4

~

15.0 4 16.0 3 17.0 3 18.0 4 19.0 4 20.0 4 21.0 4 22.0 4 23.0 4 (ponc) e f) Lh4 ) 7 0 82 Signature Date 7"30-#1 Date Signature

' Document ID: 0047W

'1 1

l 8208170359 820810 FOR USE IN UNIT I ONLY j ,

- hDRADOCK 05000289 PDR j

+ - - - . . ._,,,_..__,__;.7__ ,_ ., ,

' ~

'FOR USE IM UNIT I ONLY 1004.7 Revision 4 O ~ THREE MILE ISLAND NUCLEAR STATION UNIT NO. 1 EMERGENCY PLAN IMPLEMENTING PROCEDURE 1004.7 0FFSITE/0NSITE DOSE PROJECTIONS 1.0 PURPOSE The punose of the procedure is to provide:

a. Techniques and methods for calculating projected doses (whole body, and thyroid 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 Susqueha'nna Valley.
c. Contingency methods for estimating projected doses if monitors are out of service or off-scale high.

The Radiological Assessment Coordinator is responsible for imple-a menting this procedure.

2.0 ATTACHMENTS 2.1 Attachment I Dose Assessment Sheet 2.2 Attachment II Meteorological Data 2.3 Attachment III Calculation of the Source Tenn and Ons ~ %'cffsite Dose Projections 2.4 Attachment IV  ! . r.t t '3awy Calculations 2.5 Attachment V LN..C Release Calculation 2.6 Attachment VI Protective Action Guides 2.7 Attachment VII Field Monitoring Nomograph 2.8 Attachment VIII Computerized Dose Calculations 3.0 EMERGENCY ACTION LEVELS 3.1 As required by an Emergency Plan Implementing Procedure.

3.2 As directed by the Emergency Director or his designee.

FOR USE IN UNIT I ONLY

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~FOR USE IN UNIT I ONLY 1004.7 Revision 4 4.0 EMERGENCY ACTIONS INITIALS

NOTE: The TRS-80 minicomputer may be used in lieu of  : *
written hand calculations to detemine dose projec-, : '
tions. Utilize Attachment VIII " Computerized Dose  :
Calculations" to operate the minicomputer.  :  ;

I

NOTE: Perfom 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 perfom Steps 4.6 - 4.8.  :  !

4.1 Complete the Meteorological section of the Dose Assessment 1 Sheet by completing Attachment II. j 4.2 Complete the Release section, Source Tem and Dose Projection j section of the Dose Assessment Sheet by completing foms on s ,

Attachment III.

4.3 Utilize Attachments VI and VII to evaluate Field Monitoring data and recomend 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 l

time estimate to the Emergency Director, or his designee. t 4.6 Compile the expected downstream concentrations by perfoming  !

the steps and completing the foms in Attachment V. I 4.7 Compile the time for the fiume 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 j steps in Attachment V.

y _4 . 8 Report results to the Emergency Director or his designee.

2.0 1, FOR USE IN UN!T OlNLY i ,

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. FOR USE IN UN!T I ONLY 1004.7  :

- Revision 3 i

'O ATTACHMENT I i,

.( <<

DOSE ASSESSIENT SHEET ,  !

t 1.0 Meteorological' Section l 1.4 Pasquil Stability Class 1.1 Time 1.2 Date j 1.3 Wind Direction 2.0 Release Section f 2.1 Release Pathway  ;

2.2 Monitor Designation  !

3.0 Soun:e Tenn Calculation  !

l t

10-6 x Meter Reading x Meter Conversion - x Ventilation = Source  !

Factor Flowrate Tenn ,

. . . i uci $ fcc ) $ / l

, fcpm or cpm}

min j

[ cc }  :  :

Ci\

(secj

(

c  : (sec]  :

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k pm or min cpm) .  :  :

(-  :

x =

Noble Gas x -

t Channel  :  :  : I r

x =

Radioiodine x r Channel i

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! Source x Dispersion x 1 mph x Dose x Estimated =

Dos'9 C 1 Term Factor Wind Speed Conversion Duration (j) ,

Factor j

n . . . . . Ti.l

/Ci ) $ [Sec) $ Imph) b $ (hours) h = mrem -

2  :  : I gmph  : [ mrem hour }  :  : Z

, (sec[  : 3  :  : ci  :  :

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Channel M f

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2  :

Dose
Di stance  :

11 p-  :  :  :  :  :  :

J  :  :

400m  : EA  : 2LPZ  : SEPZ  : 10EPZ  :

3  : (arem)  :

200m

.I . . . .

'  : Whole Body  :  :  :  :  :  :  :

:  :  :  :  : i:
:  :  :  :  :  : ll

'j  :

:  :  :  : ji
Thyroid
: .

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. 1. Record the-following infomation on the Dose Assessment Sheet in the Meteorological section. '

1.1 Time of Day 1.2 Date 1.3 Wind Direction (per Recorder NWS-501E in degrees radian) l

1.4 Pasquil Stability Class (per the algorithm described below)

Is the differential temperature (dt) available?

(Recorder NWS-501E )

Yes No Is 'the wind range available?

l (Recorder NWS-501E )

Is th e > -M*R--

Yes No Yes No Stabl e Class F j3

^

Stable Is the wind range < 45'?

Class F Stable Yes l No l Class F I

Is the wind range > 75'?

Yes No Is the dt < -1.0*F?

Yes No Unstable Neutral Class B Class D

.i I

j Unstable Neutral Class B Class D

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j FOR USE IN UNIT I ONLY 1004.7 Revision 4 1

'O -

1- -

' 2. Detemine the dispersion factors that correspond to the correct stability class from Table 1, Dispersion Factors. Record the dispersion factors on the Dose Assessmefit Sheet, in the Onsite/Offsite Dose Projection section.

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 NWS-501-E in mph) on the Dose Assessment Sheet in the Onsite/Offsite Dose Projection section.

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FOR USE IN UNIT I ONLY 1004.7 l

1 Revision 3 i ATTACHMENT III Calculation of the Source Tenn and Onsite/0ffsite Dose Pmjections

1. Identify-the affected atmospheric radiation monitor (s) per the Radiation Monitoring System (RMS) Schem6 tic by comparing the " actual" indicated concentration of radionuclide to the "nonaal observed" level. If more -

- than one monitor on a Release Pathway is affected then choose the monitor furthest downstmam of the release soun:e. If all monitors in a Release

Pathway am out-of-service or off-scale then proceed to the Contingency Calculations, Attactinent IV.

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

2. Record the lloble Gas Channel and Radiciodine Channel readings for the affected monitor on the Dose Assessment Sheet in the Source Tenn Calcula-tion section.
3. Record on the Dose Assessaent Sheet in tie Source Tena Calculation section, the Meter Conversion Factors that cormspond to the affected monitor. The Meter Conversion Factors are listed on Table pmsented below:

Table 2 Meter Conversion Factors

~

Heter Conversion Factors

[ Monitor Designation : uci

Noble Gas ( uci cc }:: Radioiodine ( cc }
cpm cpm l
k /:: ( mi n )

RM-A2  : 2.52 E-08  : 8.33 E-10 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 i

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FOR USE IN UNIT I ONLY 1004.7 l Revision 3

. - l (C) 4. Detennine the Ventilation Flowrate for the affected Release Pathway. l

, J TABLE 3 VENTILATION FLOWRATE I I
s I
i i- Release Pathway ,
Ventilation Flowrate  !
: Recorder  !

li  :  ;

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

} 2 1.

2. Auxiliary Building  : 2. FR-150 4 (RM-A6)  :

>} 3. Fuel Handling Building  : 3. FR-149

^

(RM-A4 )  :

4. Reactor Building Purge  : 4. FR-148 1 (RM-A9)  :

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

.I' O 'v' ventilation Flowrate in (cc )

11 sec .

Recorx! on the Dose Assessment Sheet in the Sourt:e Tenn Calculation section j the ventilation flowrate.

5. Calculate the Soun:e Term (Ci ) as indicated by the Dose Assessment

. sec Sheet, Attachment I.

Calculate the Onsite/Offsite Dose Projections as indicated by the Dose

~

6.

Assessment Sheet, Attachment I.

7. Detennine the Emergency Action Level (EAL) utilizing Table 3 and the Exclusion Area Dose Projection.

1 a.

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FOR USE IN UNIT I ONLY 1004.7 l - Revision 3

.,m, TABLE 3 EMERGENCY ACTION LEVELS (EAL) 1: .'

3 i EAL  : Fraction of Lower Limit : Whole Body ,

l-  : Protective Action Guide : Gansaa Exposure

: at Site Boundary ('EA) 1 Al ert  : .01  : >

10 urem < 50 mrem p  :  : hour hour Site Emergency  : .05  : > 50 mrum < 1 Rem

: hour hr General Emergency : 1  : >

1 Rem /hr a

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FOR USE IN UNIT I ONLY 1004.7 Revision 3 j q ATTACHIENT IV )

Contingency Calculations )

1. Utilize Jable'l if the radiation monitors nonnally 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) . Computations shall be made using the Source Tems 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 Tenn computed utilizing Table 2 to the Dose Assessment Sheet, Attachment 1.

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FOR USE IN UNIT I ONLY 1004.7 Revisf on 3

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Contingency Calculations Table 1 r  ;

s Classification  :

Source Term (f Gisecf [
Whole Body  : T hy ruid Case I LOCA~
1. Fuel Melting  :  : ,
2. No Core Cooling  : 1.0  : 1. 5 E  !
3. 100% Noble gases and 25%  :  :

iodines in the core released to :  :

contairunent  :  :

4. Contairinent Maximum Design Leak :  :

I Rate

5. FSAR 14.2.2.4  :  :

Case 11 LOCA

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

2. ' Core cooling maintained  :  :
3. 100% GAP miease  :  :

Contairunent Maximum Design Leak :  :

4. '

Rate  :  :

5. FSAR 14.2.2.3  :  :

case III  :  :

Case Decay Tank Rupture  : 25  : 4.4 E-3

1. Total contents of tank released :  :

90,000 Ci Noble Gas,  :  :

16 Ci D.E. 1-131  :  :

2. FSAR 14.2.2.5  :  :

( 'G -' case iv  :

4.7

7.5 E-4 Fuel Handling Accident  :
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 rods suffer mechanical  :  :

damage to the cladding with GAP  :  :

miease.  :  :

3. 100% Noble Gas and 1% of the  :  :

iodine is released to Fuel  :  :

Handling Building Atmosphe m  :  :

4. Charcoal filters on FW ventil-  :  :

ation system absort 90% of the  :  :

iodine.  :  :

5. FSAR, 14.2.2.1 case v Steam Generator Tube Ruptum  : 1.0  : 9.3 E-4 Double-ended ruptum of one S/G  :  :

1.

tube  :  :

2. Radioactivity is mieased through:  :

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-  :

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REACTOR BUILDING SOURCE TERM NOMOGRAPH REACTOR BUILDING

~ (. A UNCORRECTED RM-G8

~'. READING SOURCE TERM (mR/hr) (Ci/sec)

ais'- -

n ,.-5 9

s . ' --

l .! 7 Align the uncormeted RM-G8 reading mr 1, e Tr)} with the li 3 reactor building pressure (psig). The intersection E 2.

i' point of this line with tre vertical right hand E El

!' scale is the reactor building source tern

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', 2. Reactor building source tern d 9% Noble gas d W Radiciodines 2 8

3. Containment leakrate a function of containment g.2.

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^

. ATTACHENT V LIQUID RELEASE CALCULATION

1. Estimate quantity of radioactive liquid released or the release rate o'f the liquid being released gall'ons or gpm.

(la) (1b)

2. From recorded infonnation or sample analysis determine the activity level (in uCi/ml) of the released liquid: uCi/ml.
1. (2)

?

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

i (3) a

" 4. Find the river flow corresponding to the river level No. 3 above, in 1

Table I, and record: CFS.

^

(4)

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

? active material as follows:

Maximum uCi -3 cfs uCi**

ml x pm x 2.33 x 10 gpm + cfs = ml T2T- W W l  : NOTE: ** If the average or maximum downstream concentration  :

is > 1 x 10-6 uC1/m1, notify downstream users to  :
curtail intake.  :

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- =-q FOR USE IN UNIT I ONLY 1004.7 Revision 4 ATTACHENT V Time for Flume to. Reach Downstream Users

6. Downstream Points (Table II)
7. Distance to Point in miles WW (9) (9) (9)

(Table II)

8. River velocity in mph cor-(10 ) TIOT TF TIDT F responding to river flow from (4) above (Table 1)
9. Calculate a time in hours for the fiume to reach selected point: Step 7 Step 8 y

'~ 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 unrestricted areas:

uCi _4 uCi ml x min x 6.95 x 10 = ml

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FOR USE IN UNIT I ONLY 100,,,

Revision 3 1 1

' l O ATTACHtENT V s

12. Determine the, estimated fraction of MPC:*

uCi ml + W C** = Fraction of MPC P

W w Tr2T-

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 TOCFR20.403.  :

NOTE: ** WCw is the weichted WC for the isotopes released.  :

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

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. FOR USE IN UNIT I ONLY 1004.7 Revision 3

) h ATTACHMENT V

( -

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 .

t 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

) 17.9 287.0 350,000 3.7 19.5 400,000 3.9 288.1 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 28.1 295.1 700,000 5.1 29.3 297.1 750,000 5.3 30.4 298.1 800,000 5.5 i' 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.  :

i

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. FOR USE IN UNIT 1 ONLY 1004.7

- Revision 4 i ATTACHENT V TABLE II

.; DOWNSTREAM POINTS 3

,1 Downstream Distance To Water Users User (6) (miles) (7)

Brunner Island Steam Electric Station 5.0

i Wrightsville Water '

Supply Company 16.25 Borough of Columbia 16.75 City of Lancaster 16.75

"^ Safe Harbor Water and Power Corp. 27.25 Holtwood Reservoir 34.75 Chester Water Authority 43 City of Baltimore 49 9

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. FOR USE IN UNIT I ONLY 1004.7 Revision 4 a . .

r3

.i j ATTACHMENT VI Protective Action Guides

" Actual or Projected Exclusion

. Emergency Action  :

h Level (EAL)  : Area Dose (mrem)

Whole Body  : Thyroid
1. Unusual Event  : <10  : <50
2. Alert  : >10 <50  : >50 <250
3. Site Emergency  : >50 <1000  : >250 <5000
,  : i
4. General Emergency  : > 1000  : >5000  ;

-y l

Protective Action  : Actual or Projected Exclusion Guide (PAG'S)  : Area Dose (rem)

!3 .

q "> Whole Body  : Thyroid Lower Limit (PAG)  : 1  : 5 Upper Limit (PAG)  : 5  : 25 4

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- AIRBORNE 10 DINE SAMPLE NOM 0 GRAPH 1004.7

- CPM Note: This nomograph is to be used for Iodine 131 Revision 4

-coss 'c?M-sks. C?M) air samples counted with a SAM 11. ihls nomograph gg assumes an ave. counter factor of 7800 for SAM II's.

C 131

- - 1 AirbobeA::ivi:y A1- Saa le Volume 20" (?t ) (al or ec) (uci/al).

- n z.-5 1

- 8

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. Instructions- Oraw a line through Net CPM (A)

.,,00 0 ~3

- and Air Samp e Volume (B) using a straight edge

., 3,. ,. '. and read l lJ Airborne Activity (C) on the line.

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Revision 4 a , , ,

u ATTACHENT VIII 1

1 COMPUTERIZED DOSE CALCULATIONS a _-

a

1. Ensure compute'r components are connected as pictured in Attachment 1A.
2. Energize the system components in the following order:
a. Quick Printer II  ;

- b. Video Display 4

c.

Keyboard Tenninal

, 3. Computer will respond with the following message: P EMORY SIZE - .

f

^

Strike the ' ENTER' Key

4. Computer will respond with:

-,, RADIO SHACK LEVEL II BASIC ,

READY

NOTE: For liquid release, go to step 6.  : .

i

5. For airborne release: r Place cassette labeled ' Program "D" Airborne Dose Calculations' in .

recorder and ensure cassette is rewound. Depress the PLAY button, set  ;

i volume level to '4' .  ;

I j 6. For liquid release: l t

1 Place cassette labeled ' Program "L" Liquid Release Calculations' in

. 1

^4  ?

recorder and ensure cassette is rewound. Depress the PLAY button, set 3

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ATTACHENT VIII (cont'd)

~

-! , 7. Enter thE following command from the keyboard:

CLOAD "D" for airborne; CLOAD *L" for liquid 'and strike the ' ENTER' key.

4i At this time the cassette will begin loading the program into the computer memory. Program loading will take approximately 21/2 or 3 '

1 minutes. One steady and one blinking star will appear in the upper right 6

corner of the video display to signify program loading is in progress.

NOTE: If both stars appear, wjth neither blinking; i.e.  :
both steady replace cassette with new copy and start :

"  : over at step 5.  :

a ______________________________________________--___-____---_---_------

i

8. When program loading is completed, the computer will respond with:

READY

/^)s Depress stop button, rewind the cassette and remove it from the recorder.

9. To begin program execution, enter the following command from the keyboard:

) RUN

j and strike the ' ENTER' key.
10. General notes on program operation:
a. All responses must be followed by striking the ' ENTER' key.

1

b. Numbers in scientific notation should be entered using the following formats:
)

9.2 x 103= 9.2E3 i

~

4.0 x 10-4 = 4E.4

c. All responses requiring a yes or no, are to be answered with a Y 1

t - or N.

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-110 'VAC 110 VAC 110 VAC 110 VAC

, n A ^ ^

J VIDEO DISPLAY n

! PWR

. LINE

( PRINTER Blue White Yellow TAPE Ribbon Cord

/ Red On/Off Green 2-UNIT

- g TAPE UNIT

~

. 8 Ug-Ear KEYBOARD 2. Lg. Grey Plug-Aux

3. Sm. Grey Plug-Mic a

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