ML20072L247

Public Version of Rev 5 to Emergency Plan Implementing Procedure EPIP 1004.7, Offsite/Onsite Dose Projections

ML20072L247
Person / Time
Site:	Three Mile Island
Issue date:	03/08/1983
From:	GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20072L246	List: ML20072L247
References
0047W, 47W, EPIP-1004.7-01, EPIP-1004.7-1, NUDOCS 8303310163
Download: ML20072L247 (24)

Text

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1004.7 r

Revision 5 03/08/83 IMPORTANT TO SAFETY NON-ENVIRONMENTAL IWACT RELATED THREE MILE ISLAND NUCLEAR STATION UNIT NO.1 EERGENCY PLAN IWLEMENTING PROCEDURE 1004.7 0FFSITE/0NSITE DOSE PROJECTIONS Table of Effective Pages M

Revision Page Revision Page Revision ision 1.0 4

2.0 5

3.0 3

4.0 4

S.0 4

ti.0 4

7.0 3

8.0 3

9.0 3

9 10.0 3

11.0 3

12.0 3

13.0 3

14.0 4

15.0 4

1o.0 3

17.0 3

16.0 4

19.0 4

~

20.0 4

21.0 4

2Z.0 4

23.0 4

foof s? l$N N

et.n a

STgnature 6

Date Signature Date 8303310163 830328

' ~ '

PDR ADOCK 05000289 F

PDR,

' ~

^

~^

^

^

j 1004.7 i

Revision 4 THREE MILE ISLAND NUCLEAR STATION f-UNIT'NO.1 EMERGENCY PLAN IMPLEENTING PROCEDURE 1004.7 0FFSITE/0NSITE DOSE PROJECTIONS 1.0 PURPOSE The purpose of the procedure is to provide:

a.

Techniques and methods for calculating projected doses (whole body, and thyroid dose equivalent which might result from mo d

releases of radioactive materials from TMI Unit b.

Techniques and methods for predicting the downs ncentrations of radioactive liquids resulting from a na ental release of radioactive liq e Susquehanna V 1 c.

Contingency r estimating pr op doses if monitors are out of serv ff-scale high.

The Ra ical Assessment Co or is responsible for imple-menting procedure.

2.0 ATTACHMENTS 2.1 Attachment I essment Sheet 2.2 Attachment II teorological Dat 2.3 Attachment I alculation of u e Tem and Onsite/Offsite rojections 2.4 Attachment I W Contingency Calculations 2.5 Attachment V Liquid 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.

1.0 ap %

w m-

+-ep.--

= + ' ' * "

c 1004.7

~

Revision 5 4.0 EERGENCY ACTIONS INITIALS NOTE:

The TRS_80 minicomputer may be used in lieu of written hand calculations to determine dose projec-tions. Utilize Attachment VIII " Computerized Dose Calculations" to operate the minicomputer.

NOTE:

Perform steps in order:

If the release is radioactive mate he atmosphere, perform Steps 4.1 - 4 i

If release is of radioactive li

he

~

Susquehanna River perform Ste

.8.

NOTE:

R IP 1004.6, Addition ssistance and Hot tion, Attachsen

g. 10.0) for 5

cal information.

-07 sources of meteo c

4.1 Comp he teorological f the Dose Assessment Sheet by complet Attachment II 4.2 Complete the Release Source Term a Projection section of the' Dos Ass nt Sheet by c g fonns on Attachment III 4.3 Utilize Att VI and VII to a

Field Monitoring data and rec rotective Action.

V 4.4 Utilize A hment IV to project dose based upon contingency l

l calculations.

4.5 Always report dose rate, dose, time used, and basis for the time i

estimate to the Emergency Director, or his designee.

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

f 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.

2.0 s

WP. -

s 1004.7 Revision 3 ATTACHMENT I DOSE ASSESSENT 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 Source Tenn Calculation N

7 10-6 x

Meter Readi x

lleter Conver x

Ventilation Source

=

7 Factor

.p Flowrate Tenn 3

y I Ci\\

fcp o

[

uci fcc )

sec)

(secj

(

c o

/

Noble Gas

=

I Channel Radiofodine x

=

Channel

\\

t

~

(

3.0

..,wg

.,e owe e e' W 'e

&(

• • • 6**e'B**

N

A

R

• t e

1004.7 Revision 4

.t j..

4.0 Onsite/Offsite Dose Projections t

f Dose Soun:e' x

Dispersion x

1 aph x

Dose x

Estimated

=

i Tem Factor Wind Speed Conversion Duration l

Factor N

[Se (hours)

= mism Imph) m

[C1

}

eph[

r (secj g

f f

f I

Noble Gas x

x x

4ES. d x

=

Vg I

Channel Radiciodine j

Channel

,x x

M9 x

=

V W

4 fI l

k A

Dose J

Distance h(N 200m 400m EA 2LPZ l.

10EPZ,

(area) p i/ :

itiole Body

Thyroid e

4.0

1004.7 Revision 4 ATTACINENT II C

METEOROLOGICAL DATA 1.

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

1.1 Time of Day 1.2 Date l

1.3 Wind Direction (per Recorder NWS-501E in degrees radia l

1.4 Pasquil Stability Class (per the algorithm described 1

Is the differential temperature (dt) available?

(Recorder NWS-501E )

Is the w d e available?

Yes a

l (Reco NWS-501E )

Is the dt > -0.3*F?

O Yes

.N Yes No stable Class F Stable Is the win range < 45'?

(..

Class F

~

i Class F l

No 5t&ble t--V O

s the wind range > 75'?

I K

Yes No Is the dt < -1.0*F?

Yes No Unstable Neutral Class B Class D Unstable Neutral Class B Class D 5.0 e

6 em

=

=%.M M + gW ^ e O' m Nw + 4WW+

_g 6AW e*

N

-Wwi

- mew *

• Mi s

4-----=M

• wwm-*qu'be enn-

1004.7 Revision 4 2.

Detemine the dispersion factors that correspond to the correct stability class from Table 1, Dispersion Factors. Record the dispersion factors on the Dose Assessment Sheet, in the Onsite/0ffsite Dose Projection section.

Table 1, Dispersion Factors A

Pasquil Stability Distance Class 200m :

400m EA 2LPZ(7 :315EPZ 10EPZ V

B

7./ E-4 : 2.75 E-4 : 1.1 E-4 : 2 7.4 E-7 : 4.7 E-9 D

3.8 E E-3 : 5.4 E-4 :

5.

5: 1.3 E-5 $ 5.2 E-6 i

I F

E-

3.25 E-3 : 1.

3 2.0 E-4 : 7.0 E-5 : 3.2 E-5 A

ff Record the Wi ed (per reco

-E in mph) o the Dose Assessment

(

Sheet in the Onsite/Offsite Dose tion section.

J a

6.0 e

w -

es a

8 9

~

1004.7

- Revision 3 ATTACHENT III q

I'I Calculation of the Source Tem and Onsite/0ffsite Dose Prujections 1.

' Identify the affected atmospheric radiation monitor (s) per the Radiation Monitoring System (RMS) Schematic by comparing the " actual" indicated concentration of radionuclide to the "nomal observed" level. If more than one monitor on a Release Pathway is affected then choose the monitor furthest downstmam of the miease soun:e. If all monitors in a Release Pathway am out-of-service or off-scale then proceed to the Contingency Calculations, Attachment IV.

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

2..

Record the Noble Gas Channel and Radioiodine Channel s for the affected monitor on the Dose Assessment Sheet in Tem Calcula-tion section.

3.

Record on the Dose As Sheet in the So m Calculation section, the Meter Co Factors that c rmsp to the affected monitor. The Meter C ion Factors are 14 on Table presented below:

Ta 2

Meter Co actors I

M:

Mtemnversion Fac,Aors

(

Monitor Designation :

[

}

uct Noble Ga (,q } :

cc -

Radi cc i

I V cpm cpm

[?

(

)::

b />

(

mi n /

v y

RM-A2

-08 8.33 E-10 RWM N/A RM-A5 l

RM-M 8.33 E-10 RM-A8 2.7 E-08 7.7 E-10 RWA 9 2.56 E-08

7. 2 ' E-10 7.0 i

e.

t6. A w %== dire e-ie-Am e=*'e*-*w+S'

-M

• ie*

"*******N- - * *

• • • • • 48

"**N-

'*P-

k y

A 1004.7 7 i

t DiEMATIC DRMING Revision J O

h%f-A6 2 4 RM-49 (124soacm)

(

gy.As 3 A

kW 4 ** '*)

L AuxiaseyeaaaW9 (so,oo eu)

(p';>"

~ aanewgsmas W W Y

k

]

f p

a:

e r.uas. a m ias (e,ooo eeu) u

(

autt oING

)

i 4

h i

fy I-k u

fagBd/LEWNG AIR.sAMFEING h

f

,tiscn%

^

~rei"' eu"'*

o

't:

8.0 J

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w 1004.7 Revision 3 c

4.

Detemine the Venti 11ation Flowrate for the affected Release Pathww.

.(.

i I

TABLE 3 YENTILATION FLOWRATE

)

Release Pathway Ventilation Flowrate Recorder 1.

Station Vent (RM-A8) 1.

FR-151 (

2.

Auxiliary Building 2.

FR-1 (RM-A6) 3.

Fuel Handling Building 3.

F (RM-A4 )

4.

Reactor Buildi 4.

F 3

(RM-A9)

(t k

W f

Maltiply the lation Flowrate by 472 'to obtain the ventilation Flowrate in (cc )

sec Reconi on the Dose Assessa t in the Source 1culation section the ventilation flowra 5.

Calculate the Sourt i ) as indica Dose Assessment sec Sheet, Attachne 6.

Calculate the Ons Offsite Dose Projections as indicated by the Dose Assessment Sheet, Attachment I.

7.

Detemine the Emergency Acti,on Level (EAL) utilizing Table 3 and the Exclusion Atta Dose Projection.

9. 0 4u-wes s4 we,h*

m--

.g.,,.,,.. -..,

wqg, ag g

_-..e.

2. -. -

..: u _.

..._a___,.

1004.7 Revisicn 3 TABLE 3 EERGENCY ACTION LEVELS (EAL) 7-I t

EAL

Fraction of Lower Limit :

Whole Body

Protective Action Guide :

Gama Exposure at Site Boundary (EA)

Alert

.01

>. 10 urem < 50 mrem hour Site Emergency 05

< 1 Rem hr hr General Emergency :

1

. b>v 0

@qs

c v

l s

s w

G l !

t If l

10.0 i

I N

-h-.eeaeh-m e

M-em.-e.pmy.

a mea

.-ema-sw e p q

m.w.a

,9,

1004.7 Revision 3 ATTACHMENT IV

'C.

Contingency Calculations 1.

Utilize Table 1 if the radiation monitors nomally used to monitor the containment and/or other plant effluent paths are out of service or off-scale high. The Emergency Director shall se1ect a classification from (I-V). Computations shall be made using the Source Te identified in Table 1.

Transfer the noted Source Tems to the Dose A e t

Sheet, Attachment 1.

2.

RM-G8 meter readings, containment pressure indica i Table 2 shall.

be utilized in lieu of 1 (Case I and II)

Tems when possible. Transfer e Tem compute g ing Table 2 to the Dose Assessment S tachment 1.

v e

T e

M WM eM-4 p-

• e-(P=hM^-

W*

,M

@9M+

Pm-ee

• 4 h #9A+e

.^ $ 6 -Mwe 5 -egNg

1004.7 Revision 3 Contingency Calculations Table 1 Classification Sou n:e Te nn / G1 1

\\ 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 com mieased to :

containnent 4.

Contairunent Maximum Design Leak :

Rate 5.

FSAR 14.2.2.4 A

' M ~1.5 E-3 Case II LOCA 1.

No Fuel Melting 6.5 E-2

U 2.

Um cooling maintained 3.

100% GAP miease 4.

Containment Maximum gn Leak :

Rate 5.

FSAR 14.2.2.3 N

Gase III V

\\v Case Decay Tank Ru 4.4 E-3 1.

Total con nk mieased :

90,000 C 16 Cf D.

131 f

2.

FSAR 14.2.

M:

Gase av

(

7.5 E-4 Fuel Handling Accident 4.7 1.

Reactor is S/D for 72 2.

56 Fuel rods suffer 1

danage to the cladd P

miease.

3.

100% Noble Gas f the iodine is rele uel Handling But osphe re 4.

Chan:oal fi F2 ventil- :

ation syst 90% of the iodine.

5.

FSAR, 14.2.2.1 Gase V Steam Generator Tube Rupture 1.0 9.3 E-4 1.

Double-ended rupture of one S/G :

tube 2.

Radioactivity is released through:

the turbine bypass to the con-denser and then out the conden- :

sate vacuum pump exhaust.

3.

The gas to liquid partitiqn factor for iodines is 10-*

12.0 W

+~I

J'.

1 1004.7 CONTINGENCY CALCULATIONS TABLE 2 Revision 3 REACTOR BUILDING UNCORRECTED RM-G8 SOURGE IERM NOMOGRAPH P'.

REACTOR BUILDING READING SOURCE TERM 1

(mR/hr)

(C1/sec) 7 g, g, I 1a 80 Align the uncormeted RM-G8 mading with the 7

mactor building pressum (psig). T inte rsection 5

2 point of this line with the vertical right han i.

scale is the reactor building source tern C j

15 3

4 i

REACTOR BUILDING 5.'g 2

8 PRESSURE (psig) j wa' ia n

are Q

l 7

k

-1 8

5' k(

f,f; 3

3 n

0 as 5

5 7

a Assump 3

=#

L building f ree 2E6 ft )

2 or building soun:

l'

' Noble gas I*8

, Radiof odines 3

3.

Contairnen_t leakrate a function of contairnent Ei1 p ressu re.

j 53 3

.+

.S 2

5.6 b}

13.0 j;

.. +

d a

k b

El 5

b 3 w'=----4

_g,

~ '

w d

1004.7 Revision'4 ATTACHENT V LIQUID RELEASE CALCULATION 1.

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

(la)

(1b) level 2.

From recorded infomation or sample analysis detemine the c (in uCi/ml) of the released liquid:

uCi/ml.

(2) 3.

Obtain the river level by calling the River Fo er in Harrisburg at phone number 782-225

-3488 and record ading:

_ f t.

(3) 4.

Find the river flo sponding to the ive evel No. 3 above, in Table I, and r rd.

CFS.

(4) 5.

Calculate the ave age 'and maxi ream concentrat s of radio-

{.

active material as follows:

V

^

Maxim'um uCi 3 cfs uCi**

ml ml x g

x 10 gpm +

W (IbT 'p W

=

NOTE: ** 1 the average or maximum downstream concentration is > 1 x 10-6 uCi/m1, notify downstream users to curtail intake.

5 14.0

1004.7 Revision 4 4

ATTACHIENT V Time for Flume to Reach Downstream Users 6.

Downstream Points (Table II) 7.

Distance to Point in miles WWWWW (Table II) 8.

River velocity in mph cor-WWWW responding to river flow from (4) above (Tabic 1) 9.

Calculate a time in hou v

for the flume to reac selected point: S Step 8 24 Hour Average Conc ration in Unrebd reas

10. Record the duration of the r inutes:

11. Calculate a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> averag tration in unr s areas:

uCi 4

uC a1 x 6.95 x 10

=

W l

k 15.0 y.

.e Ow-e wwy p-4

-ege---we6 *W

• g-N*"*

~'

9

1004.7 Revision 3 ATTACHIENT V 4

.r, I

k-,

12. Determine the estimated fraction of MPC:*

uCi ml

+ W C** =

Fraction of WC W

w W

If the ratio obtained in (14) of Attach

500, NOTE:

• notification of NRC is required with er 10CFR20.403. If the ratio obtained immediate notification is required R20.403.

NOTE: ** WCw ighted WC for atopes released.

If

..use 3 x 10-8

{

e t

g I

t i

1 k

i 16.0

. WP.

1004.7 R; vision 3 ATTACHENT V g

)

5 1

TABLE I RIVER FLOW VS. RIVER LEVEL A

B C

D Gauge Reading River Elevation Market Street at TMI River Flow ver (Cubic Fee $ g (MPH)

Bridge, Hbg.

(Feet Above Velocity (Feet)

Sea Level) per Secqnt 4.3 278.7

.9 5.3

.5 1.4 6.2

.7 7.1 000 2.0 8.1

.3 D

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 16.1 265.8 300,000 3.5 F

17.9 288.1 400,000 3.9 287.0 350,000 3.7 19.5 21.2 289.7

450, 4.1 22.7 29 50 000 4.3 24.3 25

.6 55 0

4.5 25.6 5

4.7 26.9 5.

4.9 28.1 6.1 0

5.1 29.3

.1 000 5.3 30.4 8.1 800,000 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.L 302.0 1,000,000 6.3 i

i NOTE:

River elevations 302.0 feet at water intake struc-ture TMI requires initiation of EPIP 1004.2 ALERT.

17.0 I

=

• Jy g$h*RM#

g

{e D*,'*

'N TO "NWF*3MT T,% g N Og*N

"#O

'N.

• 'Y"O 4

• M OEN M N d N

• N-Q-,g%eT W Sg-9 P

hMg4 * *'M-9

1004.7 Revision 4

~.

ATTACHIENT V TABLE II DOWNSTREAM POINTS Downstream Distance To e.

Water Users User (6)

(miles) (7)

Brunner Island Steam j'

Electric Station 5.0 A up!

c 5

99ty ncaster 6.75 Harbor Water an ower Corp.

27.25

{

Holtwood Reservoir Ah 34.7 A uthori City _ob re T

bV g

18.0 m.

• m-M e,d e. e-W-e m

es m

M-m he

.,w-em w.

e g

1004.7 j

Revision 4 ATTACHMENT VI Protective Action Guides I

Emergency Action Level (EAL)

Actual or Projected Exclusion Area Dose (mrem)

Whole Body Thy M 1.

Unusual Event 110 2.

Alert 1

1 0 <50 50 50 3.

Site Emergency 150 <1000

<5000 4.

General Emergency

> 1000 15000 N

D A

Protective ActioD Q' Actu 1 jected Exclusion I

Guide (PAG'S)/(A ose (rem)

{

/\\ Thyroid Lower Limit (PAG) 5 Upper Limit (PAG) 5 25 w

0 Ho 19.0

• W

,.WNGu$ Ms'

.mNm% 6

-R-Q+ 6 h ge 4-as yv-w w

ey em

.,e., peg

we.

.e.

me --

n, ATTACHtENT VII AIRBORNE IODINE SAMPLE NOMOGRAPH Note: This nomograph is to be used for Iodine 131 f,0 v s on4 I'

• hg g,)

air samples counted with a SAM II.

this nomograph 10-assumes an ave. counter. factor of 7800 for SAM II's.

e 131 1

AirbobeActivity A13 amola Volume S

20.

(Yt )

(al or ec)

(u01/,

9 6

40

-1I3 5

4

-2I3

.1-3 70-

.4I3

• 2-: 7I3 l'

~

10C=

[1E' 4-

,f-2I4 200 1.0; l I-6

'D

.a s

Q

2. 0 7I4 r

4,hI.II5 400,,

7. 05 4

.e 700 5

}7E3

-1

' 1000-N

- II6 4.:

':- 2I6

.I g_7 200C-oo4

-i

-Q

-1

~

4000

.c Instruc s: Draw a line tnrough Net CPM.( A)

~3

.,000 -

and Air Sam {"e Volume (B) using a straight edge and read 11 Airborne Activity (C) on tne line.

1.,,,..l.

.t

~.

20000

,g g_g

-5

-s

=7

-6 40000

,, g

-=

4

( '0000 2

-3

(.c0003

_1

~ I E-9 ~ '

20.0

~

.W

O 1004.7 Revision 4

~

i ATTACHENT VIII j

l -

COMPUTERIZED DOSE CALCULATIONS 4 i t

1.

Ensure computer components are connected as pictured in Attachment 1A.

2.

Energize the system components in the following order:

a.

Quick Printer II b.

Video Display Keyboard Tensinal c.

j 3.

Computer will respond w1 tne following messag EMORY SIZE _

D Strike the ' ENTER' v

4.

Computer will th:

RADIO SHACK L II BASIC NOTE:

For d

ease, go to s 5.

For airborne rel Place cassette Program "D" Airbo ose Calculations' in recorder and ensure cassette is re found. Depress the PLAY button, set volume level to '4'.

6.

For liquid release:

Place cassette labeled Program "L" Liquid Release Calculations' in recorder and ensure cassette is rewound. Depress the PLAY button, set volume level to '4'.

(

21.0

^WM M eeWe Mwm6 $se %N *g eum+ w gw eegeq p.e

.q

+ _,. _. _ ~

_y-,

1004.7 Revision 4 ATTACHENT VIII (cont'd) t 7.

Enter the following comand from the keyboard:

)

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

At this time the cassette will begin loading the program into the computer memory. Program loading will take approximately 2 r3 minutes. One steady and one blinking star will appear i per right corner of the video display to signify program loading i progress.

NOTE:

If bo ars appear, with ne bl king; i.e.

both a place cassette w copy and sta.rt :

over 5.

...........---- -9.- ----------------------

8.

When program loadi i

ompleted, the c te will respond with:

' READY I

Dep'ress stop button, rewind a

tte and remove i the recorder.

9.

To begin program execution the following m the keyboard:

RUN ano strike the 'E

10. General notes o operation:

a.

All response ust be followed by striking the ' ENTER' key.

b.

Numtors in scientific notation should be entered using the following formats:

3 9.2 x 10 = 9.2E3 4.0 x 10-4 = 4E-4 c.

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

22.0

• -4 T'S4 6""7%

$ yW1 gg-e*W*W g e4Wm g uw m *m e m>

y a.

mg

.s 1004.7 Revision 4 ATTACHMENT '/III f

COMPUTER CONNECTIONS and COLOR CODES 110 VAC 110 VAC 110 VAC 110 VAC

/g A

/\\

/%

E.

%.s 4

PWR

)

LIh PRINTER )

~

Blue TAPE 1

~

/Off 2-Ribbon Cord 5

- (SN Red Green

/

sajV TAPE UNIT ac Plug-Ear v

KEYBOARD 2.

Lg. Crey Plug-Aux 3.

Sm. Grey Plug-Mic

(

23.0

-