ML20083G297

Public Version of Rev 7 to Emergency Plan Implementing Procedure 1004.7, Offsite/Onsite Dose Projections

ML20083G297
Person / Time
Site:	Three Mile Island
Issue date:	11/03/1983
From:	Stange S METROPOLITAN EDISON CO.
To:
Shared Package
ML20083G288	List: ML20083G297
References
1004.7, NUDOCS 8401060158
Download: ML20083G297 (70)

Text

_ _ _ _ _ _ _

r . .

1004.7' Revision 7 IMPORTANT TO SAFETY T

NON-ENVIRONMENTAL IMPACT RELATED 3D -l THREE MILE ISLAND NUCLEAR STATION UNIT NO. 1 EMERGENCY PLAN IMPLEMENTING PROCEDURE 1004.7

2. OFFSITE/ONSITE DOSE PROJECTIONS Table of Effective Pages Page Revision Page Revision Page Revision Page Revision 1.0 7 31.0 7 61.0 7 2.0 7 32.0 7 62.0 7 3.0 7 33.0 7 63.0 7 4.0 6 34.0 7 64.0 7 5.0 6 35.0 7 65.0 7 6.0 6 36.0 7 66.0 7.0 6 37.0 67.0 8.0 6 38.0 68.0 7 9.0 6 39.0 7 69.0 10.0 6 40 7 D 11.0 6 41 7 12.0 7 7 13.0 7 . 7 14.0 7 4.0 7 15.0 7 .0 7 16.0 7 46.0 7 l 17.0 7 47.0 7 l

18.0 7 48.0 19.0 7 49.0 20.0 7 50.0 21.0 7 51.0 22.0 7 52.0 7 23.0 7 53. 7 24.0 7 5. 7 l 25.0 7 . 7

! 26.0 7 7 27.0 - 7 7 28.0 7 58.0 7 29.0 7 59.0 7 30.0 7 60.0 7

• / Y kw //l3N

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'y Signattite Date Signature Date Document ID: 0047W

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1 8401060158 831228 g )

PDR ADOCK 05000289 F PDR

1004.7

. Revision 7 THREE MILE ISLAND NUCLEAR STATION UNIT NO. 1 EMERGENCY PLAN IMPLEMENTING PROCEDURE 1004.7 0FFSITE/0NSITE DOSE PROJECTIONS 1.0 PURPOSE i

The purpose of the procedure is to provide: p

a. Techniques and methods for calculating projected doses (whole body, .

and thyroid dose equivalent which might result fro red releases of radioactive materials from TMI Unit

b. Techniques and methods for predicting the d concentrations of radioactive 11 uids resulting from a or idental release of radioactive li the Susquehanna Val .

c. Contingenc o for estimating p i ed doses if monitors are out of 1 r off-scale high The ogical Assessmen C ator is responsible for imple-menting this procedure.

2.0 ATTACHMENTS V 2.1 Attachment I ssessment She 2.2 Attachment I Meteorological Da 2.3 Attachme Calculation Source Term and Onsite/Offsit se Projections 2.4 Attachment IV ' 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 2.9 _ Attachment IX High Range RMS Dose Calculations 2.10 Attachment X Dose Conversion Factor Calculation i

l l

1.0 l

) 1

1004.7 Revision 7

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2.11 Attachment XI Hydrogen Purge Calculation 2.12 Attachment XII Thumbruies 3.0 EMERGENCY ACTION LEVELS

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3.1 As required by an Emergency Plan Implementing Procedure.  ;

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3.2 As directed by the Emergency Director or his designe -

4.0 EMERGENCY ACTIONS INITIALS

NOTE $ Theminicomputhrmaybeused I of written hand

cale ons to determine rojections. Utilize -

At VIII " Computerized Calculations" to .

coe e minicomput r.  :

= _ - - . tr_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

$ NOT formsthhsin ) $

If the release is' a at:tive materials to the

atmosphere, m ept 4.1 - 4.5.  :

If release loactive liquid to the  :

Susquehanna perform Steps 4.8.  :

. _____ ^- _ __ ,

NOTE: Ref o P 1004.6, Add a A sistance and  :

No ation, Attachment 41 , . 10.0) for  :

____ -.__ __ _ _ _ _ - = - -

the Dose Assessment ineet by

~

4.1 Complet e teorological secti

' completing ttachment II.

4.2 Complete the Release section, Source Term and Dose Projection section of the Dose Assessment Sheet by completing forms on Attachment III. If High Range RMS is to be utilized then refer to Attachment IX. Use Attachment X if a DCF is to be calculated. Use

. Attachment XI for a Hydrogen Purge calculation. Use Attachment XII  ;

for a Thumbrule calculation.

2.0 1

1004.7 Revision 7

)

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

4.4 dtilize Attachment IV to project dose based upon contingency 1 calculations. f the time I

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

4.6 Compile the expected downstream concentrations r orming the steps and completing the forms in Attachme 4.7 Compile the ti fiume to reach ream users and a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> averag ation by comple 19 remaining steps in Attachment 4.8 Reper its to the Emerge r tor or his designee.

O v 3.0

1004.7 Revision 5 ATTACHMENT I g

DOSE ASSESSMENT SHEET 1.0 MeteorologiIa1 Section I i

1.1 Time 1.4 Pas @il Stability Class 1.2 Date  :

1.3 Wind Direction 2.0 Release Section 2.1 Release Pattway 2.2 Monitor Designation 3.0 Source Tenn Calculation A

.N> \D 7 10-6 x Meter Rea gx ri x Ventilation = Source

/ Meter ConveA Factor \ \on\ Flowrate Tenn v:  :  :

[cp y)  :

[ uci  : [cc )  : [Cil

( in/  : ,

>  : \sec /  : (sec/

>  : /  :  :

t . . .

'N:ble Gas I Channel .

v  :

Radioiodine x x , =

Channel t

4.0

^

1004.7 Revisten 6 1

. 4.0 Onsite/Offsite Dose Projections Soun:e x Dispersion x 1 mph x Dose x Estimated = Dose l-Tenn Factor Wnd n Speed Conversion Duration Factor fC  : [Sec) .

I l mph \

)  : ( hours)  : = arem q(s [ecj : 1 I

, (mp hj  : '

urm

(m3 )

. II

(C  :

: i  : m  :

Noble Gas x x Qx 4E5 x1 =

C hannel  :  : (/  : d  :

Q . . .

Radiciodine  :  : <  :  :

Channel x x 3R9) x =

x[v 1

x Dose  : h Distance _  :

:  : :q  :  : (f/  :  :

(mrem)  : 200m  : 400m  :  : 2LPZ -

!$ Z -

10EPZ  :

:  :  : v  :  : VG 'l -

Whole Body  :  :  :  :  : jA  :

:  :  :  :  : /  :

:  :  :  :  : .V  :

Throid  :  :  :  :  :  :  : -

)

Jg ph't t't 3 3.0 g e

1004.7 Revision 6 ATTACHMENT II ETEOR0 LOGICAL DATA l

1. Record-the following information on the Dose Assessment Sheet in the _I .

Meteorological section, j-

~ l

\

1.1 Time of Day * '

1.2 Date 1.3 Wind Direction (per Recorder NWS-501E in degrees 1.4 Pasquil Stability Class (per the algorithm desc )

Is the differential temperature (dt) available?

(Recorder NWS-501E )

Yes , Is t range available?

l ( eco NWS-501E )

. Is the dt > -0.3*F?

Yes < o Yes No StaDie Class F Stable- Is the nge < 45* ?

( Class F Stable x Yes l No Class F V

, ) Is the wind range > 75*?

Yes No Is the dt < -1.0*F?

I Yes No Unstable Neutral Class B Class D -

l l Unstable Neutral i

Class _B Class D C 6.0 l

1004.7 Reviqion 6 e

2. Determine the dispersion factors that correspond to the correct stability class t

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

i Table 1, Dispersion Factors A

Pasquil Stability : Distance ,

Class  : 200m : 400m  : EA  : ZRW 5EPZ  : 10EP Z

:  :  : M:  :

B  : 7.7 E- .75 E-4 : 1.1 E-4 : E-5 : 7.4 E 7 : 4.7 E-9 D $ 3. 3 .35 E-3 $ 5.4 E- 9 .1 E-5 $ 1.3 E 5 $ 5.2 E-6 F 9  : 3.25 E 3 :  : 2.0 E-4 : 7.0 E 5 : 3.2 E-5

O  : ,:  :

Record the Wind Speed (per reco -501-E in mph he Dose Assessment Sheet in the Onsite/0ffsit o rojection secti .

=

(

7.0

1004.7 Revisit on 6

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ATTACHENT III f

Calculation of the Source Term and Onsite/Offsite Dose Projections

1. Identify the affected atmospheric radiation monitor (s) per the Radiation 1 Monitoring System (RMS) Schematic by comparing the " actual" indicated -

concentration of radionuclide to the " normal observed" level. If more i than one monitor on a Release Pathway is affected then choose the monitor  ;

furthest downstream of the release source. If all monitors Release Pathway are out-of-service or off-scale then proceed to th gency Calculations, Attachment IV.

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

2. Record the Noble Gas Channel and Radiofodine Chan ngs for the affected monitor on the D e Assessment Sheet i e ce Term Calcula-tion section.

3. Record on the Dose t Sheet in the gj: erm Calculation section, the Mete n Factors that c r s ond to the affected no, ;or. The Met rsion Factors lis d on Table presented below:

able 2 Meter s n Factors

m N mpter conversion m %

I Monitor Designation :

Noble s y ~ cc uct ):: R v

( uc1 cc }

/> cpm

/(A k cpm /:: _ ( m1n /

RS A2  : 2 E-08 8.33 E-10 RE A4 .

RSAS  :  : N/A

: 1 RS A6  :  : 8.33 E-10

: 1 REA8 -

2.7 E-08  : 7.7 E-10 )

RN A9 -  : 2.56 E-08  : 7.2 E-10 4

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8.0

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ni h, =$

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dA  :

1 L' A o@ v1 1 Cp

• e ilaoch" P e

t Q"' e 5 %  %

k "i k 4

{ k N i

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T

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1004.7 Revision 6

, 4. Detemine the Ventilation Flowrate for the affected Release PatNay.

TABLE 3 VENTILATION FLOWRATE J.,

Release PatNay Yentila n te

1. Station Vent (RM-A8) . 1. FR-1

2. Auxiliary Building  : 2. F (RM-A6)  :

3. Fuel Handling i  : 3. - 49 (RM-A4  :

4. React Purge  : FR-148

, ~

Multiply the Ventilation Flowra n FM) by 472 to '

in the ventilation Flowrate in (@

Record on the Dose As nt Sheet in the S Calculation section the ventilation a .

S. Calculate the enn (Ci ) as indic y the Dose Assessment sec Sheet, Attachnent .

. 6. Calculate the Onsite/Offsite Dose Projections as indicated by the Dose Assessment Sheet, Attachnent I.

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

10.0

L 1004,7 Revision 6 TABLE 3 EMERGENCY ACTION LEVELS (EAL)

(

: 1 EAL  : Fraction of Lower Limit : W Mle Body -

Protective Action Guide : Gansna Exposure 1

: at Site _ Boundary (EA) -

Alert  : .01  : >1 50 mrem

: hour Site Emergency  : .05  : m < 1 Rem

: ur hr General Emergency : 1  : > v1 Rem /hr

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NY ,

0

@@ v s O 11.0

i 1004.7 i Revision 7 j ATTACHMENT IV. CONTINGENCY SOURCE TERM CALCULATION Instructions for Using Attachment Four - - -

l

=  ?

1. Select a release pathway from the posted menu: .

A Case I Secondary Side Release Includes: OTSG tube rupture Loss of electric load Loss of power 01 rect steam release

-- GO TO CASE I --

B. Case II Reactor Buil Re ease v O Includes: Loss of c n cident (LOCA)

Maximum p al accident (MH )

Rod e n ident Spent accident in the RB

-- GO TO CASE II --

C. Case III Auxiliary and Fu O divig Building Release Includes: Spent fuel handli nt in the FHB Fuel cask drop g ansfer Op Waste decay t n ture

-- GO TO CASE III --

2. For.the selected re athway follow the 1 diagram and calculate the noble gas and ra dine source terms (S1 and S2 respectively).

3. Enter the following items on the dose assessment worksheet (Attachment I Section 4.0)

S1 - Noble gas source term (CI/sec)

S2 - Radiolodine source term (CI/sec)

S3 - Whole body DCF (MREM /HR/ucl/ce) 54 - Thyroid OCF (MREM /HR/uci/cc)  ;

4. Attach to the dose assessment worksheet (Attachment I) a completed l Worksheet A.

12.0

1004.7 Revision 7 CASE I: SECONDARY SIDE RELEASE -

Section A - Determine the Reactor Coolant Activity by following the flow diagram starting in the upper left hand corner then continue to Section B.

Section B - Determine the OTSG tube rupture leak Rate by following the flow k diagram starting in the upper left hand corner. Then continue to T Section C. -

Section C - Determine the transport fractions by following the diagram starting in the upper left-hand corner. Then con n

• Section D.

Section D - to do the dose assessment daciculation use th s from Sections A, B and C. Fill in the appropri s and calculate Si and S2, then proceed to Section E.

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Section E - Follow directi a ndicated at top .

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@@ v g C '

- f.

13.0

CASE I: SECONDARY SIDE RELEASE 1004.7 .

A. Reacto olant Activity Rzvision 7 l

_Is the .

RML1 (RC Letdown Monitor) -- YES -- Enter the RML1 High Reading - Al - CPM High Channel Reading in cpm available? (Y/N) Calculate the RCS Activity uc in ml - ( Al + 22) = 01 (Enter Item D1 in Section D) i i.

N0 fill in the blank and check the appropriate item in Section E C1 "RML1 High I Reading of _.__. _ CPM indicating _. uc" Al D1 ml F -------- - GO T I -------------------------------------------

Is the ,j RML1 (RC Letdown Monitor) -- YES -- i

'te RML1 Low Readin -

~~~ CPM Low Channel Reading in cpm avallable? (Y/N). ,_ _

the RCS Activlt q l

u in m) A~ 1220) - 'D1 (Enter Item D1 in Section D)

NO Fill in ti b a d check the appropriate item in Section E Cl "RML1 Low ading of __ __ CPM indicating __ uc" Al D1 ml

-- - -------- GO TO SEC NB ---------------------------- ------------

Is the  ! Q most Recent RCS Sample Gross -- YES -- RCS h in uc _.._

E r DI in Section D)

Beta Gamma Activity in uc/mi  ;

ml D1

. a v. a i. l. a b l e ?. .. (.Y. ./ N. )... . .

l NO C1 "Most Recent RCS Sample of

---

GO TO SECTION B ------- -=

-H ----------------------

RCS Activity oc 360 in ini ~~ ~ - D1 (Enter Item DI in Section D)

C1 - FSAR Assumption of 17. ff and 360 uc Gross Beta Gamma activity. (fill in the blank and cher,k the

^ ini appropriate item in $"eltibn E.)

GO TO SECTION B 14.0 ..

4 1004.7 .

Revision 7

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CASE I: SECONDARY SIDE RELEASE I

i B. OTSG Tube Rupture Leakrate I

' l'

. . . _ _ .Is the Identified RCS Leakrate -- YES -- Enter the identified Leakrate _ _ GPM in GPM D2 (Enter Ites D2 in Section D)

...a._v a_i..l. a_ b l e ?__ -( Y./..N._).

NO V in the blank and he a ropriate item in Section E.)

i ECTION C ------- ---------------------------------

2 I Is the v' Unidentified RCS Leak- -- YES -- Enter the unidentig ed e krate - GPM rate in GPM ~D'2' (Enter Item D2 in Section D) a__ va i. l a_ b__l e ?. . ( Y.. _/ N. . _).

l D2 NO F j he blank and che opriate item in Section E.)

-- T EC ION C --

i Leakrate - 400 GPM - D2 (Enter item D2 in Se 10 V C2 - FSAR Assumption of 400 GPM leakrate (Check the appropriate item in Section E) l

---

GO TO SECTION C ----------- j l

h su g. rd e 15.0 I

1004.7 Revision 7 CASE I: SECONDARY SIDE 'tELEASE

t. . Transport Fractions

- l 7 Is there a direct release of - NO - Radiciodine Transport I steam to the atmosphere (Y/N) Fraction = .007S = D3 .

(Enter Item D3 in Sect D) -

(Check the appropria t in Section E)

YES C3 - Condenser lease

=-

GO TO SE T -=

Is A fraction of total steam - NO - Radioiodin ra rt flow through the condenser Fraction = 3 hotwells? (Y/N) A 7 (Enter Item in Section D)

~

(Chec appropriate item in Section E)

YES I

O =

C Di t Release of Steam o he Atmosphere GO TO SECTION D ====- --------------

Enter the fraction of steam flow dir 6 the condenser o well as (A)

(See Table 1 " Steam Discharge Flowra Attachment IX)

Radiolodine Transport Fract - (A) *

.0075) 1 (A) ) 1) = +

= . - 03 e tem D3 in Section D)

V C3 = Combined Release of Steam to the Condenser and Directly to Atmosphere (Check the appropriate item in Section E)

-- GO TO SECTION D --

16.0

1004.7 Revision 7 CASE I: SECONDARY SIDE RELEASE

- - - - - - - - - - - - - - - - ------- WORKSHEET A ---- -- ------

D. DoseAssessmenkCalculation _

D1 - Reactor Coolant Activity in (uc/ml) from Section A ,-

D2 - Primary to Secondary Leakrate in (GPM) from Section D3 - Radiotodine Transport Fraction from Section C Noble Gas Source Term CI in (sec) - D1 . D2 . t D

Radiotodine Source Ter CI in (sic) -

0 D1 . M . D3 . 2.5E-6 S2

-- GO TO SECTION E - v S3 = 4E5 MRE S4 - 1.6E uci CC Enter S1, S2, S3 and S4 onto the Dose Assessment Sheet, Attachment 1. .

- .c 17.0

1004.7 Revision 7

___________---__________ -_-_,- WORKSHEET A -_---- --- -------- -_-------__-_-

E. Dose Assessment Assumptions (check appropriate entry and fill in the blank)

. uC -

C1-l((

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"RML1 High Channel Reading of CPM indicating mi"E A1 01 ue  ;

IZI "RML1 Low Channel Reading of CPM indica b iii" Al

^ (\ pN 01 l[l "Most Recent RCS Sample of "

M

.l[l,FSARAssum 17. FF and 360 C2-l[l "Idenc R S Leakrate of. GPM"

/> W bb*'

l[l entified RCS LejHLTg GPM".

~

<s p oz

\

l[l C2 - FSAR Ass h 400 GPM Leakr$ M

1. U AY R<, .

mW -

C3-l[l CACO nser Off-Gas Relea l[l C3 - rect Release of Steam to the Atmosphere l[l C3 - Combined Release of Steam to the Condenser Off-Gas and Directly to Atmosohere 18.0

o 1004.7

. Revision 7 CASE II: REACTOR BUILDING RELEASE Section A - Determine Accident selection by following flow diagram starting at the upper left hand corner. Then continue to Section B.

Section B - Determine the Reactor Coolant Activity by following the flow diagram starting in the upper left hand corner (2 pages). Then  ; I continue to Section C. .

Section C - To make the calculation of Reactor Building Radio concentrations, answer the question in the box th necessary calculation, then proceed to section Section 0 - To do the calculation of Reactor Building a ollow the flow diagram starting in the upper left hand c .

en continue to Section E.

'Section E - To do the cal of Reactor Building rce terms use the l answers fr ns B, C and D t g inue to Section F.

Section F - Follow di s given in prer is s.

0 v l

L g 0 19.0

CASE II: REACTOR BUILDING RELEASE 1004.7 ~

Revisirr A. Accic c Selection Is the release associated Go to Section 8 with a spent fuel handling -- NO -

accident? (Y/N)

C1 - Spent Fuel Handling Accident in the RB (Check the appropriate item in Section f YES l

l _

- er of damaged fuel rods is FSAR postulated 208 Is the number of -- - - - -

damaged fuel rods a ropriate 1 tem in Section F)

(Ch t available]_(Y/NL __ i Noble Gas j ration i

YES I uci

( cc) - 1.7 - E1 (Enter Item El in Section E) 1 a lolodine Concentration I

~i 1.5E E2 (Enter Item E2 in Section E) l

-- 0S ION O --

i Enter the number of damaged fuel rods = __ L q

! C2 - Actual number of damaged fuel rods 7j (Check the appropriate item in Section F)

Reactor Building uct </ 1 l

Noble gas concentration ( cc) - (1.7 . __ _ ) + 208  !

A1 uc! jj i 1

- _ _ _ cc - E1 (Enter Item El in Section E) j l

Reactor Building UCI

~ l

) + 208 Radiolodine Concentration ( cc) - (1.5E-3 . ~Al l 8'"

" uct

- _ ~EE - E2 (Enter Item E2 in Section E) -- GO TO SECTION D -- l 20.0

1004.7 '

)

Revision 7 CASE II: REACTOR BUILDING _ RELEASE ,

B. Reactor Coolant Activity, Cont'd lithe RML1 (RC Letdown Monitor) -- YES -- Enter the RML) high reading - Al _ _ CPM I-High Channel' Reading in cpm Available? (Y/N) Calculate the RCS Activity uc in mi - + 22) = = A2 (Enter item A2 in Section C)

• I~

"RML1 H nel Reading of CPM" Cl Check appropriate Section F) l l

TO SECTION C - I Is the RMLI low reading - Al -

RMLI (RC Letdown Monitor) -- YES -- En 4 ^ ~ CPM j

Low Channel Reading in cpm Available? (Y/N) Calculht i Activity l

l No

@l  ;

UC In ini - ( ~Al

- "RML1 Low Cha 1

- A2 (Enter item A2 in Section C) ng of __. . CPM" Al Ch c d propriate item i F)

-- TO SECTION C -- I r.

.,.e 21.0 Y

CASE II: EEIQiLEILD1mir 'SE 1004.7 -

Revisitn 7 D. R6 .cr Coolant Activity. Cont'd Based upon in-core instru-mentation does the ED -- VES -- Reactor But1 Jing notile gas concentration JussccLfuct me1 Lina?

uC mi (cc) = 5.7E3 ( cc) = El (Enter item El in Section E)

Reactor Butiding radiotodine concentration NO

' UC Ki 0 (cc) = SE2 ( cc) = E2 (Enter item E2 in Section E)

C1 = Fuel melting as indicated by in-core instrumentation (Check appropriate it Section F)

-- GO TO SECTION D -

Based upon in-core instru- [

mentation does the ED sus- -- VES -- actor Butiding noble ga ratton

_pecLfucLCladdlan dmiasel__ lI l

160 ( cc) = El eactor tne radiotodine con Lla t i Ki 1

( cc) cc - E2 NO C1 = Fuel c1 d age as indicated by in-core instrumentatten (Check appro a1!e + m n Section F) i

-- GO TO SECTION --

nter RCS Activity in el - -

(Enter item A2 in Section C)

Most Recent RCS Sample Gross - VES --

. ticta SMI!hlhtlYitY.1tL uc/mL C = b st Recent RCS Sample N t d ppro;rtate item in Sect F)

-- TO TION C --

NO ---------------------------------- React ildt ble gas concentratton

~

WC '

(ml) = 160 = I (Enter item El in Settton E) }

Radiotodine concentratton lI WC (ml) = 13 = E2 (Enter item E2 in Sectios. El ,

Cl = "FSAR assumed fuel cladding damage" (Check appropriate item in Section F

-- (X) TO SECTION D -

h e r. e%t 22.0

1004.7

• Revision 7 ,

CASE II: REACTOR BUILDING REl. EASE C. Calculation of Reactor Building Radionuclide Concentrations

. . . . . _ _ l __ ___ _

i I-ls the total number of gallons of RCS leakage into -- NO -- (Check the appropriate item in Section F) the Reactor Building available? (Y/N) Reactor Build le gas concentration I uct

j (~cc) = 160 - El ite'm El in Section E)

L/ #)olodineconcent

( c) 3 - E2 (Enter it E2 in Section E)

-- GO TO N D --

Enter the al ntnber of gallons = _

A3 (Enter item A3 below) o gallons of RCS leakage into the OC2-Actualn IG e ppropriate item in Section F) actor Building (C Calculate the Reactor Building Noble Gas Concentra i n ( c)

( A2 . A3 . 2950) + 5.6E10 = __

= El (Enter item El in Sectio I uti j Reactor Building Radiolodine Concentration ( cc) = ,

( A2 . A3' . 56) + 5.6E10 =

= E2 (Enter item E2 in Section E)

-- GO TO SECTION D -- ,

23.0

1004.7 -

• Revision 7 CASE II: REACTOR BUILDING _ RELEASE D. Calculation of Reactor Building Leakrate

.._...____...] ' l A4 - 50.6 psig I-Is the actual Reactor Building internal pressure -- NO -- C3 - FSAR postulated RB pressure of 50.6 psig indicated on PT-291? (Y/N)

(Check th priate item in Section F) y Enter item A4 nd perform the calculation YES I i Enter the actual pressure ____ - A4 C3 - Actual RB internal pressure (Check the appropriate item in Section F) j

@ 4 cc - l - --

Calculate the actual RB leakrate (sec) l CC

- (656

• A4~ 2) -

_ _ (sic) - E3 (Ente item E3 in Section E) l

( 50.6 ) ;j

-- GO TO SECTION E -- v

24.0 " r ' '

1004.7 Revision 7 .

HORKSHF ) _

CASE II: REACTOR BUILDING RELEASE ,

E. Calculation of Reactor Building Source Terms Enter Items 51, S2, S3 and 54 Noble gas source term ( )

onto the dose assessment

' sheet, Attachmenti1.

-( E1 . E3 ) + IE6 - S3 - 4E5 MREM Si R

.uct CI cc Radiolodine source term (sec) 1

-( E2 . E3 ) + IE6 - S4 = 1.6E9 uc CC F. Dose Assessment Assumptions (Check the box and fil e nk items if applicable) l l C1 - Spent fuel handling accident in the Reactor Buildt med 208 l~ . l C2 - Number of damaged fuel rods is FSAR l l C2 - Actual number of damaged fuel rods 4

l jl C1 - RML1 high channel reading of _ CPM Jj Al lJl C1 - RML1 low channel reading of ____ _. CPM A1

~

j '. l C1 - Fuel melting as indicated by in-core instrumen to

)

l_l C1 - Fuel cladding damage as indicated by in-core instrumentation j

l ~~ l C1 - Most recent RCS sample l1l C1 - FSAR assumed fuel cladding damage l_l C2 - Actual number of gallons of RCS leakage into the Reactor Building 4

l_l C3 - FSAR posty, lated RB pressure of 50.6 psig l l C3 - Actual RB pressure of _ __ psig A4 25.0

1004.7 Revision 7 CASE III: , AUXILIARY AND FUEL HANDLING BUILDING RELEASE Section A - Follow the accident selection flow diagram and then continue to e the section indicated by the answer, (yes or no). 1 Sections B, C, D, and E .[

In these sections do the necessary calculations to t the answers .

51, S2, and Cl, then continue to Section F. -

Section F - Fill out sheet completely.

O o+  ?

@@ v s 0

- =

26.0

1004.7 Revision 7 CASE III: AUXILIARY AND FUEL HANDLING B'JILDING RELEASE A. Accident Selection -

I T Has a grab sample been obtained of the affected -- YES -- GO TO SECTION I area and analyzed on a geli spectrophotometer? (Y/N)

N0 Does the accident e fuel assembly da e -- YES -- GO T CTION C spent fuel pool?

v D Doestheaccidentinvolvegs-fuel cask drop during tr n YES -- GO TO D far operation? (Y/N)

NO Does the a e involve -- YES GO TO SECTION E a waste gas easn? (Y/N)

NO - GO TO SECTION F --

" .c 27.0

1004.7 Revision 7 CASE III: AUXILIARY AND FUEL HANDLING BUILDING RELEASE

8. Source Term Generation Based Upon a Grab Sample j.

CI  :

Calculate the noble gas source term in (sec) where ,

B1 - total of noble gas isotopes as indicated in samp B2 - ventilation flowrate from affected building in Noble gas source term = x x _gI B1 82 Si sec CI Calculate the radi i i source term in g here B3 - total o lodine isotopes n 1cated in sample B2 - venti flowrate from building in CFM CI Radiolodine source term - x 4. 4 (iec) g B2 S2 Enter 82, 51, and S2 in et F Enter the Time /Date he ample in the b b ow C1 - Grab sample on a gelt s h eter at Time /Date (Check the a r te item in Section d fill in the blanks)

-- GO TO SECTION F --

2  :

28.0

1004.7 Revision 7 CASE III: AUXILIARY AND FUEL HANDLING BUILDING RELEASE C. Fuel Assembly Damage in the Spent Fuel Pool .

C_I_ 4.2 7 Noble gas source term (sec) - S1 (Enter S1 and S2 in Section F) * ,

~

CI 7.5E-4 Radiolodine source term (s E) = S2 C1 = FSAR postulated fuel assemoly damage in the sp 1 pool (Check the appropriate item in Section F)

- GO TO SECTION F -

D. Fuel Cask Drop Duri er Operation ter S1 and 52 in Section F)

CI 1.2E-3 Noble gas so r (s E) = S1 CI Radioiodine rce term (sR) SA?

C1 - FSAR postulated fuel cas op during transf p ration (Check the appropriate Section F)

-- GO TO SECTION F G

L 29.0  !

i

1004.7 Revision 7 CASE III: AUXILIARY AND FUEL HANDLING BUILDING RELEASE E. Haste Gas Decay Tank Rupture 1 CI 26 I Noble gas source term (s E) - 51 (Enter 51 and 52 in Section F) ' .

CI .004 Radiolodine source term (s R) = S2 C1 - FSAR postulated waste gas decay tank rupture

.. .c ..p,op,,.t. ,t.m ,n S.ct,on ,,

-- GO TO SECTION F --

g D

0 4

0@ v s O 30.0

1004.7 Revision 7 CASE III: AUXILIARY AND FUEL HANDLING BUILDING RELEASE F. Dose.dtssessment assumptions -

(Check the box and fill in applicable items) [

A I l[lC1-Grabsampleanalyzedonagelispectrophotometerat

/Date l[lC2-Ventilationflowrateof B2 CFM l[,lC1-FSARpostulatedfuelassemblydamageinthe pool l[lC1-FSARpostulatedfuelcaskdropduringtr er ration l[lC1-FSARpostulated s decay tank ruptur 51 - D S2 - n )

53 - 4E5 HR/uci/cc)

S4 = 1.6E9 (MREM /HR/uci/cc)

Enter Items S1 S2, 53, Mto the Dose As ssme Sheet, Attachment 1.

g C

. =

31.0

1004.7 Revision 7 ATTACHMENT V LIOUID RELEASE CALCULATION

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

(la) (lb) .

2. From recorded information or sample analysis determine th t ity level (in uC1/ml) of the released liquid: ?C1/ml.

(2)

3. Obtain the river level by calling the River Fore a h er in Harrisburg 9

at phone number 782-22 82-3488 and rec reading: ft.

4. Find the river f r ponding to the ri N vel No. 3 above, in Table I, and c CFS.

(4)

5. Calculate the rage and maxim wn eam concentr ions of radio-active material as folicws:

?Cl 3 cfs ?Cl**

ml x g 33 x 10 gpm + - ml (2) (Ib) (5)

NOTE: f the average or maximum downstream concentration

is ),1 x 10-* ?C1/ml, notify downstream users to  :

curtail intake.  :

- r 32.0 l

1004.7 Revision 7 ATTACHMENT V (Cont'd) -

Time for Flume to Reach Downstream Users

6. Downstream Points (Table II) ,

7. Distance to Point in miles ~

(9) (9) (9) (9) (9)

-(Table II)

8. River velocity in mph cor- &

(10) (10) (10) (10) (

responding to river flow from (4) above (Table 1)

9. Calculate a time in ho for the fiume to rea selected point:

Step 8 24 Hour Average Concentration in U h ed Areas

10. Record the duration of t w se in minutes: in.

11. Calculate a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> ge oncentration i e r cted areas:

?Cl .. &

l ml x n x 6.95 x 10 - m1 l

(Sa) (1) (1) i l

=

l l 33.0

1004.7 Revision 7 ATTACHMENT V (Cont'd)

12. Determine the estimated fraction of MPC:*

. q

?C1 -

mi + MPC.** = Fraction of NPC  :

(13) (12) .

NOTE:

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

notification of NRC is required wi s per  :

10CFR20.403. If the ratio obtaine ,000,  :

immediate notification is requi CFR20.403.  :

NOTE: ** MP weighted MPC or th sotopes released.  :

wn, use 3 x 10- ' .  :

34.0

1004.7 Revision 7 ATTACHMENT V (Cont'd)

TABLE I I

RIVER FLOW VS. RIVER LEVEL e i A B C D [

Gauge Reading River Elevation I Market Street at TMI River Flow iver Bridge, Hbg. (Feet Above (Cubic Feet ocity (Feet) Sea Level) per Sec _ _

(MPH) 4.3 278.7 , .9 5.3 279.5 , 1.4 6.2 280.1 60, .7 7.1 80.7 0.0 0 2.0 8.1 .3 000 2.3 10.4 8 .5 150,000 2.6 12.5 83.6 D 00,000 3.1 14.3 284.9 250,000 3.3 l 16.1 285.8 300,000 3.5 17.9 287.0 350,000 3.7 19.5 288.1 400,000 3.9 l 21.2 289.7 450,0 4.1 22.7 291. 500,0 4.3 24.3 292. 55 0 4.5' 25.6 00,00 4.7 26.9 0 4.9 28.1 7 0 5.1 29.3 2 , 00 5.3 30.4 298.1 000 5.5 31.3 299.2 50,000 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: Rberelevations302$bfeetatwaterintakestruc-  :

ture TMI requires initiation of EPIP 1004.2 ALERT.  :

35.0

1004.7 Revision 7 ATTACHMENT V (Cont'd)

TABLE II DOWNSTREAM POINTS

= ,t Downstream Distance To User

[

Water Users .

(6) (miles) (7) -

Brunner Island Steam Electric Station 5.0 Wrightsville Water Supply Company IL2 o b m Cl O aster \ 75 or Water v

nd wer Corp. 27.25 twood Reservoir A 34.75 h Chester Wat Authority 4b />

City M \

g b

- =

36.0

1004.7

. Revision 7 ATTACHMENT VI Protective Action Guides / Protective Action Recommendation ProtectWe Action  : Actual or Projected Exclusion i Guide (PAG'S)  : Area Dose (rem)  ;.

Whole Body  : Thyroid .

Lower Limit (PAG) $ 1 $

Upper Limit (PAG)  : 5 4

0 O v s 0 e

37.0

1004.7 Revision 7 LOGIC DIAGRAM DEVELOPwENT OF PROTECTIVE ACTION RECOMPENOATIONS (PAR)

SITE OR GENERAL EMERGENCY CONSIDER SHELTERING DECLARED FOR A SIGRIFICAt4T EXCLUSION AREA PRO- ~~~~~~~~""~~~~"

j" ~ ~

• JECTEG-DOSE RESULTING }

l FROM A PVFF RELEASE .

No EPA - PAG'S (lower LIMIT) vES _ EPA - PAG'S (UPPER LIMIT)-

EXCEEDED OR PROJECTED EXCEEDED OR PROJESTED

• TO BE EXCEEDED 7 TO BE EXCEEDEDr ,

MO i

UNCERTAIN l

I ELTER g LARGE FISSION PRODUCT UNCERTAINTY AS TO DIUS ===

NVENTORY IN CONTAINMENT 7 y THE RELIABILITY Op DOWNw!ND PLANT FUNCTIONS TO SUFFICJENT TO EXCEED EPA - PRO ECT THE P L!C PAG S LOWER LIMIT)

SEE NOTE G NO YES IS RELEASE l DURATION EXPECTED l SUBSTANTIAL CORE TO BE LONG g

g A E PROJECTED I FUEL DAMAGEl.. NO NO y $2 CAN EVACUATION RECOMMEND I

I j( ^ SE ACCOMPLISHED PRIOR T P UME SHELTERING OF ALL POTENTIALLY I,,

CONTINUE NO ' S4g TAINNENT INTEGRITY LED OR PRO ECTED ARRIVAL.2)

NOTE SEE AFFE D ASSESSMENT AREA TO FAIL

( NO YES YES Ng A

RECOMMEND CAN EVACUATI . EVACUATION YES ACCOMPLISHED P ! A TO 0F AFFECTED P(UNE A %! AREALS)

LSEE l Y_ .

k RECOMMEND EVACUATION RECOMMEND SHF.LTER n_ F EA(S)

OFAFF(C]ED THAT CANNOT BE E ATE 10R AREAL $i

== TO PLUME ARRIVAL D ND EVACUATION OF OTH EA(S) l (SEE NOTE )

i NOTE 1; CON!!DERATION SHOULD SE GIVEN TO THE. PROJECTED EXPOSURE 70 BE RECEIVED TO A PERSON IF HE SHELTERS VICE EVACUATES. IN S0 D01NG, YOU MUST FACTOR #ELEASE DURAT10N, RELEASE MAGNITUDE AND AS$UME A P80TECTION FACTOR OF /. FOR UP TO THE FIRST Z HOURS OF RELEASE DURATION AND A PF 0F 1 FOR > 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> RELEASE DURATION. THE PATHWAY OF LEAST EXPOSURE'SHOULD BE CHOSEN.

NOTE 2: TMI EVACUATION TIME ESTIMATES LOWER (hours) UPPER (HOURS)

( .

BEST EST! MATE (NIGHT) 9 8.

TYPICAL WEEKDAY (NORMAL) . .

ADVERSE WEATHER . 1.

I LowET - GOOD STATE OF EME8GENCY RE ADINESS (Slow SCENAR!O)

UPPER - LACK 0F ADE0uATE PREPARATION TIME (FAST SCENARIO) {

NOT{ $t IN EXERCISING THE JUDGMENT AS TO THE NEED FOR PROTECTIVE ACTICN #ECOMMENDATIONS, ANY UNCERTAINTY CONCE8 MING THE STATUS OF PLANT FUNCTIONS NEEDE9 FOR PROTECTION OF THE PUBLIC, THE LENGTH OF TIME THE UNCERTAINTY EXISTS, THE PROSPECTS FOR EARLY RESOLUTION OF AMBIGUITIES, AND THE POTENTIAL DEGRADATION CF THE #LANT FUNCTIONS NEEDED FOR PROTECTION OF PUBLIC SHOULD RE CONS!DFRED; !.E., SIGNIFICANT UNCERTAINTY AS TO THE oELIABILITY OF PLANT FUNCTIONS TO P8078CT THE puBLIC EXTENDING 3FYOND A PEASONABLE TIME PERIOD IS A SUFFICIENT RASIS FOR MAKING A PROTECT!vE ACTICN *ECOMMENDATION TO SHELTER WITHIN A 2 NILE RADIUS OF THE PLANT AND 3 MILES DOWNWIND. CONTINUE PLANT ASSESSMENT.

l 1

38.0 l

l l

- - ~ .- ,

ATTACHMENT VII 1504.7 Revision 7 yhCPM AIRBORNE 10 DINE SAMPLE N N '

(Gr:Oc CPM-Bkg. cDO note: This no.ograph is to be used for Iodine 131 0" air samples counted with a SAM II. This nomograph C-assuines an ave. ' counter factor of 16000 for SAM II's. 333 I AirbchneActivity

, gg L --

(Ft ).

3, (al or cc) (" ' 5 40.,

s

= a

.p -

=2E3

., > E-6 100- .1- . ,,

4E3

. 2- (7,3 200- 4 ' 1E4

. :p y2E4 -3 1.0 . D ~7 400,,

4E4

~'

, 2. 0- -7E4 -

-4 700,,, 4, o- -I ,,,

" 00 ,,

2000 - 1E6 70 --2E6 -e 100 h 7, 4000,,,

-s

• 4 7000 '

7 -'

• E-8 10000 , "

-2 20000 ,

Instructions: Draw a line through Net CPM (A) .y{

-7 and Air Sage Volume (B) using a straight edge ~*

40000 - and read I Airborne Activity (C) on the line.

.s LO 3 N E .NOVOGRA+ -,EE-9 100000  : -2

• Is 39.0

1004.7 Revision 7 l ATTACHMENT VIII COMPUTERIZED 00SE CALCULATIONS

1. Ensura. computer components are connected as pictured in Attachment 1A. -

2. Energize the system components in the following order: f l

a. Quick Printer II I

b. Video Display

c. Keyboard Terminal

d. Expansion Interface

3. Computer will respond the following mes .

MEMORY SIZE -

D Strike the 'ENT K

4. Computer wi sp with:

RADIO SHACK L II BASIC READY

_ -- A - - ------ ___ -----

NOTE: o ading Unit II progr s o Step 7.  :

5. For airborne -

Place cassette led ' Program "D" Airborne Dose Calculations' in recorder and ensure cassette is rewound. Depress the PLAY button, set volume level to '4'. -

6. For 11guld release:

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

40.0

1004.7 Revision 7 ATTACHMENT VIII (Cont'd)

7. For Unit II airborne release with RMS system in-service and on-scale:

Place 2. cassette labeled "EMERG2" Unit II Emergency Dose Calculations' in 7

~

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

volume level to "4". -

8. For Unit II airborne release with RMS system out-of-serv e or off-scale:

Placecassettelabeled"EmergencyContingencyCaldO{n s" in recorder and ensure cassette is und. Depress the utton, set volume level to "4".

D

9. Enter the folio g and from the k oa CLOAD "D" f it airborne; CLO Unit I liquid; CLOAD "EMERG2" for II Emergency a ulations; CLO " CONT 2" for Unit II Emergency Contingency Calcu ns and strike t E ER' key. At this time the cassette w 1 b n loading the p m nto the computer memory. Program loa w take approxim 1 2 or 3 minutes. One steady and one bl ar will appear th pper right corner of the video display o y program loadi i n progress.

---

-------=__ --_=------------ .------------------

NOTE: If both stars appear, with n"ither blinking; 1.e.  :

both steady replace cassette with new copy and start :

over at step 5.  :

i

---

_= --_ --- --------------- ------------- _-

l l

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

l l READY l

?

Depress stop button, rewind the cassette and remove it from the recorder. ~

41.0

1004.7

. Revision 7 ATTACHMENT VIII (Cont'd)

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

RUN _. I and strike the ' ENTER' key. [ '

12. General notes on program operation:

a. All responses must be followed by striking the 'EN .

b. Numbers in scientific notation should be enter g the following formats:

9.2 x 10 - 9.

.. 9 4.0 x 10

c. All r ses requiring a ye o , are to be answered with a Y or N. V

@ v s 0 42.0

1004.7 ATTACHMENT VIII - evision 7 COMPUTER CONNECTIONS

.:. AND COLOR CODES _

J

~

110VAC 1 VAC ligVAC  % VAC s m V N_ VID

< DIS s >

so * \N .

EXPANSIO ON/0 .- g INTERFAC YELLOW _E TAPE PRINTER 2 UNIT WHITE 3-ON/0F GREEN KEYBOARD

~

c TAPE UNIT

1. Black Plug - Ear

2. Lg. Grey Plug - Aux.

3. Sm. Grey Plug - Mic.

l 1004.7 Revision 7 ATTACHMENT IX HIGH RANGE RMS DOSE CALCULATIONS e- Section A - System Description i The High Range RMS is categorized into three distinct subsystems (See

[

Schematic):

1. Radiolodine Processor Stations

2. Containment Air Sampling

3. High Range Noble Gas Channels Subsystem (1):

Radiolodine Processor St t i 9

Three stations allow mpi to be obtained dep dent of radiation monitors RM-AS. A8 and A9 e s ations are con solenoid valvas which actuate flow throug ne or more of 3) arallel filter cartridges per station. The sampling times for a lter cartridge ustable on each local control panel. The fil ridges must be m removed for analysis.

, Subsystea (2):

Containment Air Sa 1 The post accident RB spheric sampling station is located at the 322' level of the intermediate building, one floor above radiation monitor RM-A2.

Three-way ball valves are installed in the RM-A2 sampling lines downstream of containment isolation valves. The sampling lines are connected downstream of CM-VI, CM-V2, CM-V3 and CM-V4 at P-108.

44.0

1004.7 Revision 7 ATTACHMENT IX HIGH RANGE RMS DOSE CALCULATIONS SUBSYSTEM 3: HIGH RANGE NOBLE GAS CHANNELS MONITOR  : EFFLUENT  : DETECTOR  : RANGE  : CONVERSION  : FLOWRATE DESIGNATION : PATHWAY TYPE  : ?C1/cc  : FACTOR CPM /?ci/cc : CFM RECORDER-RM-A8G High : Aux and FHB : GM Tube  : IE-2/1E-3 : IE3  : FR-151 -

RM-A9G H1gh : RB Purge  : GM Tube  : 1E-3/IE2 : 2. 3  : FR-148 RM-G24  : RB Purge  : Ion Chamber  : IEl-1ES  : .  : FR-148 RM-A5 High : Condenser  : GM Tube  : IE-3/1E2  : '3  : See Table 1

Off-Gas  :  :  :

RM-G25  : Condenser  : I r  : IE1/1ES  : 1.5  : See Table 1

Off-Gas  :  :

: D.  :

RM-G26  : A, B Main  : S i tillation : I /1E  : 1020  : See Table 1

,  : Steam L .  :  :  :

RM-G27  : C, D  : Scintillation - 1E3 : 1056  : See Table 1

Steam L1 - -

f

• MR/HR/ ?ci /c'c

<+

1 f

e 45.0

,Th ~

p , '

1004.7 lilGil RANG S Revisio.

h Il l A IREACTOR BUILDING PURGE DUCT)

-RM-A9G lilGil

-RH G24

()

TI

~-

-RAD 1010 DINE PROCESSOR STATION l

i g. ( ;~'

(f)

AllXILIARY III HUILDING . - - -

l. ,

".E I

l (STA Jk. C

-RM- A8(Nil 7,-

-RADIO 100 OR STATION I flEACTOR ~! '

FUEL llAllDLillG IlulLDING ---

BUILDlHG p/3-

~s-g-

IlERE l

CONTAINHENT Ih) AIR SAMPLING ilH-G26 Ril-G21 ( f 4 (ATHOSPilERIC DUMPS)

(MAlti STEAll REllEFS) - h (C0flDENSER OFF-GAS) j 10RillilE -RM- A5 111Gil .

BillLillflG -RM-G25

-RAD 1010 DINE PROCESSOR STATION o,.o' n

46.0

1004.7 Revision 7 ATTACHMENT IX HIGH RANGE RMS DOSE CALCULATIONS

- Section B - Source Term Calculations 1 1.0 Calculation of the Radiciodine Source Term utilizing the Radioiodine [ '

Processor Station. -

1.1 Enter the radiotodine concentration in microcuries c etermined per EPIP 1004.31 from the silver zeolite cartr ge.

I131 pct /cc Il32 ci/cc i Il33 c  !

I134 1135 cc Total .C cc D

()

1. ~4 Enter i re se flowrate i eet per minute (CFM) as determi from the Tabl w:

Release Pathway S X Y Release Flowcate (CF@ -

Station Vent  : FR-151  :

RB Purge Duc b  : FR-148  :

See Tab

Condenser O W-G4 Release Flo (CFM)

(B) 1.4 Calcula e adiotodine Release ce Term utilizing the following equation:

Radioiodine Release concentration (pC)/cc) x Flowrate (CFM)

(A) (B) x Curie Conversion x Flowrate Conversion Radiciodine Source Factor IE-6 CI Factor 472 cc - Term CI ci sec sec CFM

^

1.5 Go to Attachment 1, Section 4.0 " Dose Assessment Sheet" s-47.0

1004.7 Revision 7 TABLE 1 Steam Discharge Flow Rates (1) Steam Generator "A", "B" Valve Tag No. Steam Flow #/hr. Press. PSIG - ,

MS-Vl7A. MS-V178, C and D 792,610 1050 .

MS-V18A, MS-V188, C and D 799,990 1060 MS-Vl9A, MS-Vl98, C and D 814,95 1080 MS-V20A, MS-V208. C and D 82 1092 MS-V21A, MS-V21B 4, 1040 MS-V22A 212 200 MS-V228 v D 6,793 200 (2) Steam dischar c , steam Generator B im lar for Valve MS-V17C, D MS-V18C D - 9C O, MS-V20C, -

B. (MS-V22B is 76,793 #/hr at 200 PSIG)

(3) Steam Dump to Atmosphere Q B

% Valve opening deman eam flow #/hr.

20 1.77 x 10 5 40 3.6 x 10 5 5 60 5.09 x 10 5 80 5.61 x 10 100 5.767 x 10' (4) Condenser Vacuum Pump Discharge Path To be read from flowmeter on the pumps, or if unknown, use 20 SCFM.

(5) In the event of a direct release of steam to the atmosphere utilizing RMG-26 or MRG-27 to monitor the source term; the following term shall be included with the release flowrate:

Total Steam Flowrate RMG-26 or RMG-27 Steam Flow Past 48.0

. =,. ;

s4- . 1 1004.7 ct t; .

t Revis4on 7 4ff._.

g s ..

r.t.z*

w<!*- / . 1 Y. f.**. -

)~ {

{

.f.*...* '

b i

a 1

.,",@ et l- 1' e l

, $ l f+ ee.P.v'. s .

- ,s p

M 60 a~~

I REACTOR BUILDING LEAK RATE 1

an.7

.w-M' 1..

M .

j

\

.* I s , , -

. = =_:  ;

-.%.y.y 55 - -

n w- g  % m 1 I L l

' Ne . U

, _ 1 w I Ei

-,n. .

d ,. _.

. n ,

m . s 4,y . .. -

G , . -

u w

Y y 1

-- .' . , M m

. , _ m s' . -. .

<. E E

n -

w--AA R

I v

- n

-s wr .-- -us a _

.g m,

2

)# g p,t gg

• 3s ar -

=

93 ,

A M

, m "W- .

M.m

_M .

.- E Fa%1' q E . # 1 g .. - - - , .

.s.. y.;

. c ._.

s..

. ~ .

. u, - ,. m _ .

a.

.: =

w _=. - . _-., _. _

.; w. r,. !*, - - := .- . .

w - ._ .,

c u, . - ,

. . , r,,,

m .

ti. , < m .

.m. .,

w a ?. * , . .

,c -

a. .. . .

c, . . -.

. . . . w .... .

. . =

.~ ~

. g :

o .. . .. .

s . .

y .- . . ., u w i w .

, f, - ,..

.m.

2 ..- m - , ..

.7,. , ;. * . ~, . .,., m,-,.

e . _ ,. - . .

... , 2 - -

( ,... . a.

. wg -

- '. 15 -

A

,6 a-10 y1.< . .: .- .

1

^--

Oh '.* '

% ,1, 5

u. - > ,

r. ,. ._

.m -  :

m ' -

0_

% -) 4 5 6 7 8 9 0 1 2 3

• .t.J

w. a 6

REACTOR BUILDING LEAK RATE cm s?.

(CFM) a-(

W.i re w .%n. .

DD. 49.0

..N. . -..

. - - . - . - . , , , , , , . - . _ - - . . , . n.,, ,- , - , . - - - . . . - - , , , , - - _ - - - . . , - - . - - - -_ _ _ _ _ _ .

1004.7 Revision 7 ATTACHMENT IX (Cont'd) 2.0 Calculation of the Radiolodine and Noble Gas Source Terms utilizing the Containment Air Sampling Station. 7.

2.1 Enter the Containment Air Sampling Bomb Radionuclide Concentrations {

in microcuries per cubic centimeter (pcl/cc) as deter ned per EPIP 1004.31:

Noble Gas Nuclides Ra e Nuclides KR85 pci/cc pct /cc KR85m pci/cc Il pci/cc KR87 /cc 133 pci/cc KR88 M c 4 pct /cc XE133 N cc I 35 pct /cc XE133m & 1/cc Total dine pci/cc XE135 (T T T pci/cc (A2 )

XE135m m (hV pei/cc pci/cc Total Noble Ga f(Ai)

.V l 2.2 Enter the Reactor Build e se flowrate as termined from the Table below: Relea w e CFM

(  : Purge Va Qn FR-14 y -

' $ Purgt losed See leg $

v v 2.3 Calculat Noble Gas Release Source Term utilizing the following equation:

i Total Noble Gas x Release Flow x Flowrate Conversion Concentration pg Rate CFM Factor 472 cc (A1) cc (B) sec CFM Curie Conversion x Factor 1E-6 C1 - Noble Gas pci Source Term _C1 ,

Sec 50.0

1004.7

. Revision 7 ATTACHMENT IX (Cont'd) 2.4 Calculate the Radiolodine Release Source Term utilzing the following equation:

Total Radioiodine Release Flow Flowrate Conversion .

Concentration gci x Rate CFM x Factor 472 cc  ;

(A2) cc (B) Sec .

CFM Curie Conversion x Factor IE-6 C1 = Radioiodine pc1 Source Term _Ci Sec 2.5 Go to Attachment 1 Section 4.0 " Dose A sm Sheet" 3.0. Calculation of the and Radioiodine Sou Term utilizing the High Range Noble h els. \2S 3.1 Enter e Gas Channel rea n in CPM: CPM (A) 3.2 Enter t meter convers et as identified in Section A:

CPM or MR (B) HR Enter the p ed mixture conversi or as identified in Table 3:

'(81) kcM s. Mix gc1 Cal. Isotope CC Enter the nuclide class fraction as identified in Table 4:

gci Noble Gas (82) cc gc1 Pos. Mix CC 3.3 _ Enter the Release Flowrate in CFM as identified in Section A:

CFh (C) 51.0

o 1004.7 Revision 7 3.4 Calculate the Noble Gas Source Term in curies per second (CI/SEC) utilizing the equation below:

Noble Gas Channel + Meter Conversion .

Reading (CPM) X Factor CPM or MR X uci Pos. Mix -

(A) (B) HR (Bl) cc 7 dcc Cal. Isotope cc uci Cal. Isotop0 ,

x pci Noble Gas x Release Flow x Rei s rate (B2) cc Rate CFM 1 n 472 3 gci Pos. Mix (C) sec cc CFM X Curie Conversion Noble Gas 1E-6 CI = Source Ter R CI (0) 9 3.5 rm curies per second (CI/SEC)

Calculate as foi  : @lolodineSource 3.5.1 nter the Noble . S e term as cal ulated in Step 3.4: CI ec 3.5.2 Enter on of Radiolo termined from Tabi Radiolodine (E) Fraction 3.5.3 he fraction of le s as determined from le 4: Noble Gas (F) Fraction

- 3.5.4 Determine the Radiolodine source term utilizing the equation below:

Radiolodine Noble CI Noble Gas X Fraction + Gas (D) sec (E) (F) Fraction

- Radiotodine Source Term CI ~

(G) sec 3.6 Go to Attachment 1, Section 4.0 " Dose Assessment Sheet" 52.0

1004.7 Revision 7 ATTACHMENT IX (Cont'd)

TABLE 3 Postulated Mixture Conversion Factor (gc1 Calibration Isoto,e to uci Pos. Mixture) s CC CC -

MONITOR  : EFFLUENT  : CALIBRATION : CONVERSI -

f DESIGNATION : PATHWAY  : ISOTOPE FACTOR C '

ci/cc RM-A8G High : Aux and FHB : XE133  :

RM-A9G High : RB Purge  : XE133  : 7 RM-G24 RB Purge -

KR85 0.01 RM-A5 High  : Co  : XE133 0.6

0 -  :  :

: 9 RM-G25 n er  : X 133  : 0.6 as  :  :

RM-G26  : A, B Main  :  : 0.007

- Steam Lines  :

0.005 RM-G27  : C, D Main R85  : 0.007

Steam Li .  :

• 0.005 1o.,n.s.,,eassugeasedu,_,,.nt t.

% O

=

53.0 l

1004.7 Revision 7 ATTACHMENT IX (Cont'd)

TABLE 4 Nuclide Class fraction Of Postulated Mixture (p_ci Pos. Mixture to p_cl Nuclide Class) -

CC CC ,

MONITOR NOBLE GAS  : RADIO!0 DINE .

DESIGNATION -

FRACTION -

FRACTIoli RM-A8G High  : 0.94  : 0. 7 RM-A9G High 0.94 RM-G24 0.94 -

.07 RM-A5 Hig  : 1.00 -

0.0008 RM-G25  : 1.00 -

0.0008 D .

RM-G 0:: *

O.  : 0.06

0.  :

0.24

- 27  :  : 0.06 0.24 g C '

I l

l l

l I

l 54.0 l

l

a 1004.7 Revision 7 ATTACHMENT X. DOSE CONVERSION FACTOR CALCULATION

--- --------- - Instructions for using Attachment X - ------

1. Select a DCE. calculation from the posted menu: 1

~

A. Whole body.DCF calculation based upon gamma spectrum analysis.  ;

-- GO TO SECTION A --

B. Thyroid DCF calculation based upon a gamma spectrum analy s

-- GO TO SECTION B --

C. Whole body DCF decay correction (assumes I hr ela from original sample analysis).

-- GO TO SECTION C --

D. Thyroid DCF decay n (assumes I hr 17 d time from original sample ).

-- GO TO SECTION E. Default DCF (D ) calculations

-- GO TO SECTION E --

2. For the selected DCF calculati mine the whole thyroid DCF, S3 and S4 respectively.

3. Enter the following item e dose assessment r et (Attachment I Section 53 - Whole body DCF M /uct/cc)

S4 - Radiotodine DCF M/HR/uci/cc)

4. Attach to the dose assessment worksheet (Attachment I) a completed Worksheet B.

55.0

1004.7 Revision 7 A. WHOLE BODY DOSE CONVERSION FACTOR (WBDCF) CALCULATION

---

-- ------Utilizing the Attached Worksheet---

1. EntertheDIte/Timeofthesampleanalysis.

2 EC .

2. Enter Concentrations in (cc) for the listed nuclides in column 2 -

3. Multiply the concentration of the listed nuclides (column 2) b t photon energy (column 3) to obtain the photon contribution ).

Enter the Photon Contribution in column 4.

4. Determine the total concentration of the listed nuclide ng items a.-m. of column 2. Enter the Total IConcentration a te .

5. Determine the total photon tion of the listed lides by adding items a.-m. of column 4. e Total Photo h ibution as item A2.

6. Enter items Al and A2 tion A-1. Cal te WBDCF on the worksheet as item .

@@ v s O

=

56.0

1004.7 Revision 7

---

WORKSHEET B ----

WBDCF Calculation Sampie e- -

Date/ Time ,

i COL 1 COL 2 COL 3 Nuclide Concentration Photon Energy PM ibution a.) KR 85M X .18 b.) KR 85 X .0022 / -V c.) KR 87 3 .79 d.) KR 88 X 2.2 -

e.) XE 133M /> \ X .02 -

f.) XE 133 X -

M A

-) XE 135M X _\\

. . . > XE 135 .26 ,

1.) I 131 .39 -

j.) I 132 x X 2.2 3 -

k.) I 133 --

X .6 -

1.) I 134 X 2.6 -

v c.) I 135 1.5 X -

Total Conc. - Total Photon Cont. =

Al A2 Equation A-1 WBDCF Calculation:

WBDCF in MREM HR_ r uct CC Sample Date/ Time 2.1 x 10'

=( A2 + Al ) . 9E5 - 53 57.0

1004.7 Revision 7 B. THYROID DOSE CONVERSION FACTOR (TDCF) CALCULATION

--- - - - - - - - - - - - - - - Utilizing the Attached Worksheet - ----

~

1. Enter the Date/ Time of the sample analysis. ,

2. Enter the Sample Concentrations in pci/cc for the listed nuclides in column 2. .

3. Multiply the nuclide concentrations in column 2 by the isotope column 3 to obtain the isotope contributions (column 4). Enter the Isotop C butions in column 4. M

4. Determine the total concentration for the listed nuclid ng items a.-e. of column 2. Enter the Total Concentration as item A1.

5. Determine the total isotope ibution for the 1 uclides by adding items a.-e.

of column 4. Enter the To s De Contributiqn as i A2.

6. Enter items Al and A2 n B-1.

7. Calculate the TDCF 1 equation B-1. n the TDCF as item S4 on the worksheet.

O v s O

? -  :

58.0

1004.7 Revision 7

- - - - - - - - - - - - - - -------- WORKSHEET B ---- -

- Thyroid DCF Calculation .

Sample .

7 Date/ Time .

COL 1 COL 2 COL 3 &

Nuclides Concentration Isotope DCF m t ons

a. I 131 1.6E9

b. I 132 7 7.9E7

c. I 133 v 5.4E8 D

d. I 134 4E7

e. I 135

al Concentration - To o

@ pe Contributv l Equation B-1 TDCF Calculation:

l TDCF in MREM HR uCi cc

-( A2 + Al ) .- 54 i

59.0

1004.7 Revision 7 i l

C. WHOLE BODY DOSE CONVERSION FACTOR (WBDCF) DECAY CORRECTION

-- - ------------- Utilizing the Attached Worksheet ----- - - - - - - -

1. EntertheDIte/Timeoftheoriginalsample.

2. Enter the Original Concentraticns in pci/cc for the listed nuclides in column 2. i ,

3. Multiply the original nuclide concentrations (column 2) by the re ing fraction (column 3) to obtain the present concentration (column 4). En. r resent Concentrations in column 4. Factors in column 3 account for decay.

4. Multiply the Present Concentration (column 4) by the photo * (column 5) for the listed nuclides to obtain the photon contribution (colu nter the Photon Contributions in column 6.

5. Determine the total concent for the listed n cl by adding items a.-m. of column 4. Enter the Total e Concentration tem A1.

D

6. ntribution for e1 ed nuclides by adding items a.-m.

Determinethetotalph@M of column 6. Enter th Photon Contrib t a item A2.

7. Enter items Al an in equation C-1.

8. Calculate the HBDCF u 111 zing equati . Enter the HBDC n the worksheet as-item S3.

9. The elapsed time between the o concentrations a cal u ated HBDCF is 60 minutes. Determine the date/<: he calculated D adding 60 minutes to the original sample time. Ente b / time on the ee .

- f.

60.0

- 1004.7 Revision 7

---

- - - - - - = - = - - - - --- WORKSHEET B ---- ------------ - -

2 (WBDCF Decay Correction) -

~

Original Concentration Date/ Time ,

A -

COL. 1 COL. 2 COL. 3 COL. 4 COL. ) COL. 6 Original Remaining Present 'T y Photon Nuclides Concentrations Fraction Concentrations Der Contributions

a. KR 85M 0.86

b. KR 85 0 .0022

c. KR 87 .79

d. KR 88 0.78 2.2

e. XE 133M 0.987 .02

f. XE 133 0.995 f 3 XE 135M 0.08 y .5

h. XE 135 0 6 i 1. I 131 9 .39

j. I 132 74 > 2.2 3

k. I 133 0.97 .6

1. I 134 > 0.45 2.6

m. I 135 0.90 1.5 Total Present Total Photon Concentration - Contribution -

Al A2 Equation C-1 NBDCF Calculation:

HBDCF in MREN HR uci Date/ Time cc of decay corrected DCF

=( A2 + Al ) . 9ES = S3 61.0

1004.7 Revision 7 D. THYROID DOSE CONVERSION FACTOR (TDCF) DECAY CORRECTION

-- ----- -- ----------- Utilizing the Attached Worksheet ----- - - - ----

1. Enter the D te/ Time of the original concentrations.

2. Enter the Original Concentrations in pct /cc for the listed nuclides in column 2. ,

3. Multiply the original nuclide concentrations (column 2) by the ng fraction (column 3) to obtain the present concentration (column 4). Present Concentrations in column 4. Factors in column 3 account f decay.

4. Multiply the present concentration (column 4) by the is t (column 5) for the listed nuclides to obtain the isotope contributions (co - Enter the Isotope Contributions in column 6.

5. Determine the total concen for the listed nucl s by adding items a.-e. of column 4. Enter the total entration as ite 9

6. Determine the total i ontribution for he ted nuclides by adding items a.-e.

of column 6. Enter t 1 isotope contri u on as item A2.

7. Enter items Al a in equation 0-1.

8 Calculate the TDCF utilizing equati -hEntertheTDCF ltem S4 on the worksheet.

.. The elapsed time between the o cencentrations a d ca ated TDCF is 60 minutes. Datermine the date/ the calculated T b dding 60 minutes to the l

time of the original sample he date/ time h ksheet.

l l

62.0 l

1004.7 Revision 7

---

- - - - - - - -- ==-- WORKSHEET B - - --

c. THYROID DCF DECAY CORRECTION 1

~

Original Concentration  ;

A -

COL. 1 COL. 2 COL. 3 COL. 4 COL. ) COL. 6 Original Remaining Present I Isotope Nuclides Concentrations Fraction Concentrations /7@DCMeM Contributions

a. I 131 0.996

b. I 132 7.9E7 c.1 133 5.4E3

d. I 134 0.45 4E7

e. I 135 0.90 1.6E8 M V Total Tot Isotope Concentration ution =

Al A2 Equation 0-1 TDCF Calculation: @

TDCF in MREM HR ,

uci cc

=( A2 + Al ) = S4 Date/ Time

- r 63.0

^

1004.7 Revision 7 E. DEFAULT DOSE CONVERSION FACTOR (DDCF) CALCULATION

-- ----- ----------- Utilizing the Attached Worksheet - -- -

1. EntertheDiIte/Timeofreactorshutdown.

Enter the Date/ Time of the requested (DDCF) calculation. i 2.

3. Determine the time since reactor shutdown by substracting the tim tem 2) from the time (Item 1).

4. Select the proper accident classification from column 1. t is item.

5. Select the proper " time after Rx S/D" from column 2-10. this item.

6. Enter the whole body dose co ion factor (WBDCF) thy id dose conversion factor

(TDCF) as items S3 and S4 rksheet.

9 O

@@ v s O l

l -

t -

{

64.0 l

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

1004.7 Revision 7 HORKSHEET B =- -

DDCF Calculation

1. Reactor shutdown Date Time i

2. ODCF calculation Date Time -[

3. Time (hrs.) from Rx SD Hrs.

-N Column 1 Co) 2 l Col 3 l Col 4 l Col 5 l Col 6 l C 8 l Col 9 l Col 10 Accident TIME FROM REACTOR SHUT DOWN S Classification 0 1 2 4 6 A -

. 10 12 24 OTSG Tube Rupture WBDCF 2.1ES 1.8E5 1 1.0E5 8.0 6. 5.5E4 4.8E4 3.3E4 TDCF 5.8E8 6.1Ebl.5E5 4E8 7.1E8 7.7  % 4E8 V

9.lE8 9.8E8 1.3E9

' Fuel Handling (RB) -/

WBDCF 2.7E4 p.7E4 2.7E4 2.7E4 2.7E4 2.7E4 2.7E4 TDCF 1.2E9 e 1.3E9 1. 4E 9_ 1 1.4E9 1.4E9 1.4E9 1.5E9 Feel Handling (FHB) T V HBDCF 2. ( 4 2.4E4 2. E 4E4 2.4E4 2.4E4 2.4E4 2.4E4 TDCF 1 1.6E9 1.6E9 1  ; .6E9 1.6E9 1.6E9 1.6E9 1.6E9 Rod Ejection M WBDCF 1.4E N 1.2E5 1.1E 9.0E4 8.5 8.1E4 7.8E4 7.2E4 TDCF 1.2E9 1.2E9 1.3 .

9 1.4E9 1 1.4E9 1.4E9 1.5E9 N

e Gas WBDCF 5.5E4 4.9E4 .9E4 3.5E4(

y,3.1E4

.2E4 2.9E4 2.7E4 TDCF 5.4E8 6.1E8 7.7E8 8. 5ER< 9.7E8 1.0E9 1.2E9 Others V

)V HBDCF 8.2E5 7. 6.0E5 4.6ES 3 .0E5 2.6E5 2.2E5 1.3E5 TDCF 3.8E8 N 5.3E8 6.2E8 A. 7.4E8 7.9E8 8.3E8 1.0E9 HBDCF -

TDCF - S4 -

65.0 j

ATTACHMENT XI. HYDROGEN PURGE CALCULATION 1004.7 Revision 7 The RAC shall complete this attachment should the Emergency Director (ED) decide that a hydrogen purge of the reactor building (RB) is necessary in compliance with EPIP 1004.4 T**c 3.1.2.b. The purpose of this procedure is to provide the (ED) with guidelines for the

tor building ventillation flowrate.

1. Date Time

2. OotainandInalyzeareactorbuildingpost-accidentsampleinaccordancewithEPI) 1004.31 Item 4.8. Determine the noble gas and radiolodine airborne concentrations in accordance with EPIP 1004-7 Attachment IX Item 2.1. List the noble gas airborne a concentration (Item A1) and the radiolodine airborne concentratio (Item A2) below.  :

Noble gas airborne concentration (A1) uCi (3)

Radiolodine airborne concentration (A2) \

y uC1

( CC)

D

3. Determine the dispersi or (X/Q) at the xcl on area (EA) in accordance with Attachment II. List t dispersion fac o (a Item A3) below.

E ion area (EA) dispe i actor (A3) se

( 3) meter

4. Determine the whole body and t ose conversio a (DCF) in accordance with Attachment X. List the who b F (WBDCF) as 4 elow. List the thyroid DCF (TDCF) as item A5 below.

Whole MREM (A4) HR Thyroid DCF MREM (AS) HR l uC1 CC l

5. Calculate the (RB) ventillation flowrate that corresponds to 1000 MREM whole body dose rate as shown below. HR 2.2 x 10' + ( (A1) x (A3) x (A4) ) = (A6) CFM

6. Calculate the (RB) ventillation flowrate that corresponds to 5000 MREM thyroid do$e committment as shown below. Hr 1.1 x 10' + ( (A2) x (A3) x (AS) ) = (A7) CFM

,. Compare calculated (RB) venitilation flowrates (items A6 and A7). Choose the most limiting of items A6 and A7. Explain to the ED that this flowrate would yield i

exclusion area dose rates consistent with EPIP 1004.4 criteria. Also, that continuation of the ourge for one hour would yield dose rates consistent with the EPA lower limit PAG's.

66.0

1004.7 Retfision 7 ATTACHMENT XII THUMBRULES .

---

--- Instructions for Utilizing Annex I - = -- -- - --

1. Identify the release pathway. Select an effluent monitor. 7

2. Select the appropriate thumbrule form Table 1 or 2.  ;

~

3. Complete the worksheet by calculating the ratio of actual to ass d conditions for the listed parameters. As an example; RM-A5 is reading IES CPM (Enter in Col. B)

Condenser off-gas flowrate is 10 SCFM (Enter in Col. -

The dispersion factor at the exclusion are la IE-5 e E r in Col. D)

Thumbrule No. I from Table 1 ld be utilized. T ksh et should completed as follows:

Affected Ratio Ratio C Correctio t? orrected Corrected Monitor Col. B Col. D 5D FactoA \ Dose Rate Dose Rate RM-A5 IES .1 E-5 .1 . .01 MR .01 x .005 -

1E6 1E-4 . HR 5~-5 MR

_HR The correction factor is the pr he individual param ratios. The corrected dose rate is the product of th co tion factor and u orrected dose rate.

4. Enter the corrected dose n dose assessm k eet (Attachment VI). Attach to the dose assessment wo t a completed Work . Enter "thumbrule" in items Si, S2, S3, S4 and SS. M s

=

67.0

1004.7 Revision 7 ATTACHMENT XII - TABLE 1 -

Low Ranje RMS Thumbrules for Dose Protection G = Gaseous Channel RI - Radiciodine Channel

~

Column A Column B Column C Column D Column E {

Monitor Reading Ventilation Dispersion D Flowrate Factor _b ose Rate REM /HR CPM CFM sec/M W < WB

1. RM-A5G 1E6 20 1E 4 .01

2. RM-A8G 1E6 IES -

50

3. RM-A8RI 1E4

• IES -

100 **

4. RM-A9G IE V SE4 \D E-4 25

5. RM-A9RI 1 v

5E4 b IE-4 50 **

• CPM MIN

• • MREM Thyrold Dose Committment HR

^

---

-- -- - kSHEETD - -

Affected Ratio i Ratio C c o Uncorrected Corrected Monitor Col. B 1. C Col. D h r Dose Rate Dose Rate DN y

68.0

1004.7 Revision 7 ATTACHMENT XII - TABLE 2 -

.~

High Range RMS Thumbrules for Dose Protection G = Gaseous Channel

-  ?

Column A Column B Column C Column D Column E [

Monitor Reading Ventilation Dispersion Oose Rate (CPM) . Flowrate (CFM) Factor ( MEM/HR(WB)

H < )

1. RM-A5 High (G) 1E6 20 1E 25

2. RM-G25 (G) 3E3

• 20 t - 1

3. RM-G26 and 27*** IE3 5.6E6 ** < 1E- 5

4. RM-A8 High (G) IE 1ES 1E-4 450

5. RM-A9 High (G) 1E 1E4 y 1E-4 20

6. RM-G24 (G) / b .

• 1 , IE-4 10 m

HR

% T

• • lb Release via the conden f s

- WORKSHEET D = -N -

Affected RatiokN io Ratio ction Uncorrected Corrected Monitor Col. B N Iol. C Col. D Factor Dose Rate Dose Rate

- r 69.0

_ ..