ML20107F508

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Eab & LPZ Doses from Millstone Unit 3 Loca
ML20107F508
Person / Time
Site: Millstone Dominion icon.png
Issue date: 03/28/1996
From: Eakin W, Marzilli D, Miller D
NORTHEAST NUCLEAR ENERGY CO.
To:
Shared Package
ML20107F497 List:
References
M3LOCA94-01048, M3LOCA94-01048-R3, M3LOCA94-1048, M3LOCA94-1048-R3, NUDOCS 9604220353
Download: ML20107F508 (42)
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Text

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' JECT EAB and LPZ Doses BY DWM/WJE DATE 3/20/96 from a MILLSTONE CHKED DATE UNIT 3 LOCA CALC # M3LOCA94/ 01048 - R3 Rev 1 SHEET 1 OF 29 Title Page Calculation # : M3LOCA94 / 01048 - R3 . Rev.1 Interface /

Distnbution date sent NDSF CTP TITLE- EAB and LPZ Doses from a MILLSTONE UNIT 3 LOCA Total Pages: 29 plus Total # of Alphanumeric Revision Pages: 0 Total # of Attachment Pages: 0 Total # of Appendix Pages: 650 Total # of Document Pages: 679 Prepared by: I Date 3h0/% '

liam J Eakin Prepared by: I 1 / a / Date _2 70 k[ i I '

7 avid W. li l Reviewed by: 8 + Date O Donald W. Miller

/

b ll kevii W Approved by: N- Datef '4r f 4 Raymond A. Crandall CCN #

Superseded by :

Method of review:

9604220353 960416 PDR ADOCK 05000423 P PDR

~- - ,.-.-

i l

SUBECT _ . d3 and LPZ Doses BY DWM/WE DATE 3/20/96 i;om a MILLSTONE CHKED DATE UNIT 3 LOCA CALC # M3LOCA94/' 01048 - R3 Rev 1 SHEET 2 OF 29 Calculation Data Sheet NUSCo Calc # : Ei3to(491/ 0104 - R,3 I (prefix) ' (sequential (suffix) Latest number) Revision # I _

A/E Calc #/other :

CCN # 1 1

Superseded by :

Responsible discipline A b atncirAt M#DsacW0 QA(y/n) computer l Plant P.A. # ComponentID code used rev. #/ level l IdGT I PMMS code Reference Reference Building system component Drawings sh. Calculations 4O

4 SUBJECT EAB ud LPZ Doses BY DWM/WJE DATE 3/20/% l l

from a MILLSTONE CHKED DATE

UNIT 3 LOCA CALC # M3LOCA94/ 01048 - R3 Rev 1 SHEET 3 OF 29 b

4

1. Table of Contents J

1 1

TitiePage...........................................................................................................................1 l

, Pahd ation Data Sheet .... .................... ... .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ........... .. . ... 2

1. Table of Coutents....... . . . . . . . . . . . . . . ...................................3 l
2. List of Tables.. . .........................................................3 2
3. Purp= ........................................................ _................................................5 )
4. Discussion .... ... . ......................... ...... .... ................. . . . . . . . . . . ... ... 5 1

.................................... ........................................,...............5 \

J 5.1.TACTIII...................................................................................................................5  !

i 5.2. Reicase Cases... ............. .. .......... ..... . .. . .. .... .. .. ... .. . . . . . . ...........6 5.3. Source Term Basis... ....... .... ...... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .6

, 5.4. lodine Removalincontainment... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. .. 7 \

. 5.4.1. DF Defined fu. dultiple Time Release .. . .... .................7 i l 5.5. Dose Conversion l'adors.= . . . . . . . . . . . . .................8

6. Analysis: ........ . ......... . .. ... ....................................8 6.1. Time Line... . .. .. . . . . . . . . . . . . . . . . . . . . . . . . . :8 6.2. Aeenmptions.. . . . . . . . . . . . . . . . . . . . . . . . . . .8 i

6.3. Caa'da-ent Volumes, Mixing, and Sprsys ...... ..................................12

. 6.3.1. Containment Volumes... .. .. .. ....... . .. . . . . . . . . . . . . . . . . . . . . . . . .. . . .. . . 12 l 6.3.2. Mixing and Spray Effectiveness . .. . . . . . . . . . . . . . . . ......................12 4, 6.4. Releases into Caa*=t=aat ..................... . . . . . . . . . . . 13 6.5. Domatamination Factors ..... . . . . . . . . .......................15 4 6.5.1. Time to Achieve Maxunum Elemental Iodine Spray DF=200.... . . . . . . . . . . . . . . . . . . . 16

6.5.2. Time to Achieve Particulate Iodine Depletion of 50.. .. ...... . . ..... . . . . .. . .. . 16 4 6.5.3. Caa*d-aa' B pass 3 leakage.. ... .. . . . . . . . . . . . . . . . . . . . . 16 1 6.5.4. Containment Filtered leakage.. . . . . . . . .. . . . . . . .. . . . . . ... 16 6.5.5. ESF leakage ... . . . .... .... . . . . . . . . . ...............................17 6.6. leak Rate Discussion.. . . .. . . . . . . .. . . . . .... . . . .. . . . . . . . . . . . . .. . 17 j 6.7. Thyroid Dose Conversion Factors ... . .. . . . . . . . . . . . . . . . . . . . . . . . .. 17 6.8. C_ =_=_*~

. Code input Data Sets .. .... .. . . .....................................Ib

.9 r_ =~. *~_

- - . - . . . . . . . . .........................2

7. Conclusion . . ...... ......... . . ............ ... .. ...... .. . . . . ... .... . ... .. . .. . .. .... . . . 26
8. Cabdanon Phnrahat .......... . .............................,.........27

)

4

9. References ................... . ..... ... ..... . .... ......... .. .. ..... ..............,.....................28
10. . . . . . ......................................................... ........................29
10. Appendix A: EXCEL Si o.E-w: Functions and Formulas ......... ............. ...... . .. . .. .. . . ... ... 30
11. Appendix B
Reviewer's Co:nmente .. .........................................................35 i 12. Appendix C: TACT III Output... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 38 i

4

2. List of Tables i Table 1 Reg. Guide 1.4 vs. Timing Only Release.. .. . ... . .. . . ........................................7

. Table 2 Time Line of Significant Events...... .. . ...... . . . . . . . .9 Table 3 General Assumptions - Apply to All Cases.. ... . . . . . . . . . . . . . . . . . . . . . . . . . . . . .10 Table 4 Spray Assumption: - All Cases .. ..... . . . . ... .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

,10

Tabic 5 Bypass Case A --wians... .. . . . ... .. . 1 1 Table 6 Filtered Case A.a.sumptions., . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . .... . .. .. . 1 1

. Table 7 ESF Case Assumptions ........... . ..... . . . . . . . . . . . . . . . . . . . . . . . . . . . -12 4

7

w..._.._- -_._...a..-- - .w.._a.._....-,_..

SUBJECT EAB and LPZ Dc. ,:, BY DWM/WJE DATE 3/20/96 from a MILI. STONE ,

CHKED DATE UNIT 3 LOCA CALC # M3LOCA94/ 01048 - R3 Rev 1 SIIEET 4 OF 29 Table 8 All Cases: Spray Volumes, Mmag and Filter Rates as a Function of Time.. .... ....... ..................... . . .12

Table 9 Release Activities.. .. .......................................................... .................14 l Table 10 Sprayed and Unsprayed Node Fractions.. .... ...... .. ... ................................ ...... .. .. . 14 Table 11 Isotopic Releases by Node . ... . ... . .. 15 Table 12 Thyroid Dose Conversion Factors.. .. . . .. . .. . ..... .. ... . . . . . . . . . . . . . ................17 Table 13 Tact III Input Data Set -(Caani-ant Bypass Leakage).. .... .. . .. . . . . . ...... 18 Table 14 Tact III Input Data Set - (Containment Filtered Leakage).... ... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 19 Table 15 Tact 111 Input Data Set - (ESF Leakage) .. . . . . .. . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 21 Table 16 ICRP 30 Thyroid Dose Adjustment (Contamment Bypass Leakage) . . . .. ....................23 l Table 17 ICRP 30 Thyroid Dose A4em..e= (Containment Filtered leakage).. . . . . .... 24 l

Table 18 ICRP 30 Thyroid Dose Adjustment (ESF I rakage) ; , . . . . . . . . . . . . . . . . . . . . . - 25 l Table 19 EAB 0 2 Hour Dose Calculation Summary... .. - 26 Table 20 LPZ 0-30 Day Dose Csiculation Summary.......... .... ... ... .. ..... . . ... . . . . . . - 26 1

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amm . _._. . _ . - . m . .. ._s .

I SUBJECT E. ' Doses _ LY DWM/WJE DATE 3/20/96 frou a b JtDNE ~

CHKED DATE UNJ" 3 C CA CALC # M3LOCA94/ 01048 - R3 Rev 1  ;

SHEET 5 OF 29 i 3.

Purpose:

This calculation is being performed to reanalyze the Mdistene Unit 3 Design Basis Analysis (DBA)

LOCA Doses using revised assumptions. Doses will be calculated for the EAB and LPZ. Upon approval this analysis will supersede QA Category #1 calculation M3LOCA94/01048-R3, Rev. 0 (Ref.1). His calculation is being done in support of FTSCR #3-25-95 (Ref. 21).

His calculation also damaastrates the use of revised radiological source term --a*iaa= This radical change from past practice is being conducted as part of an ladustry (NEI) effort, coordmatad with the NRC, to demonstrate the applicabality of the Bevised Source Ierm (RST) NUREG-1465 (Ref. 9) to l

existing light water reactors. Mdistone 3 is a " pilot plant"in this effort, ne asmmptions included here ,

are one approach to the application of the RST, which we are calling the " Timing Only" option. l l

4. Discussion i Revision 0 to this calculation (Ref.1) was performed to support TSCR 3-16 94. Telephone ramments made by the NRC indwa that the interpretation of SRP 6.5.2 Rev. 2 (Ref. 8) used in that calc was incorrect. De NRC has verbally indicated that, contrary to what the SRP indicates, one cannot use both ,

50% inaraneananne plateout and particulate plateout removal ofiodme in containment. Prehminary verbal j indications are that the 50% plateout is not preferred. Thus, the spray removal methad is used here. j i

TSCR 3-16-94 is still pending. Herefore the current li~a lag basis for Millstone 3 is supported and  !

analyzed in QA Cat I Calculation #88 019-%RA, Rev. 2, Ref. 6. Upon issnanne of the emandmant for this (PTSCR 3-25-95) change, it is expected that TSCR 3-16-94 will be withdrawn / superseded-There are three different classes of ====ations that change in this cale compared to Ref. 6.

1. Two major design assumptions change as a result of the FTSCR: the Containntent Design IAskrate was changed from 0.3%/ day to a proposed Tech. Spec. limit of 0.65Wday, and the Enclosure Bmiding (SLCRS) drawdown time changes from 2 minutes to 30 minutes.
2. There are changes to detailed assumptions reDecting plant configuration changes and the results of updated calculations and references, (e.g., mixing rates and pH control).
3. The RST Timing Only assumptions are a significant change to the assumptions used in performing this calculation. However, one of tb: fundamental principals of the Timing Only proposal is that the methods remain the same, even though assumption values (e.g., release i time) may change - The principal difference in the Timing Only proposal is in the time of release of radiannelidae from the fbel, which changes from release of applicable inventory at j t=0, to a release of the gap activity at t=30 sec and a release of the r-aiaia: applicable
inventory at t=30 min. Details = specised in the .-mwons .ac*ian below.

Method:

5.

5.1. TACTlil

The TACT Ill (version 83.0) (Ref. 4) computer code was used in this analysis. TACT 111 (ver. 83) was
validated per NEO 2.24/QS-3 and was last benchmaied on Sept. 14,1995 since its prior benchmark of Mar.15,1995. TACT 111 " simulates the movernent of radioactivity released from a reactor core as it migrates through user def'nad regions (nodes) of the cantninment,. is immnhilized by filters and spmys, and leaks to the outside envirnamant Outputs are shown for the end of each time interval and include the l

I

__..-_.m.. _ _ . , _ .

SUBJECT EAB and LP2 Doses BY _I"VN#WJE DATE 3/20/96 from a MILLSTONE CHKED _. DATE UNIT 3 LOCA CALC # M3LOCA94/ 01048 -R3 Rev 1 SHEET 6 OF 29 level of radioactivity in each node of the matainment and in the environment, broken down as iodines, noble gases, and solids...; and the radiation dose to reference individuals at the exclusion radius, the boundary of the low W=*ian zone,'and in the control room." (Ref. 4).

A two node (sprayed /unsprayed) ma'alamaa' martel is used. Mixing rates have been calentanart by Stone i

& Webster.

6.2. Release Cases The MP3 IDCA dose is calm 1= tart from 3 separate component release cases (see Figure 1):

1) " Bypass Case" cantainment bypass leakage
2) " Filtered Case" Cantainment filtered leakage
3) "ESF Case"- ESF BnMng leakage Figure 1 Release Node Diagram s a,,c - V ed v =

- esassa XY uC Q

a=rw.a

  • ces.hm raw.41.e.,.

ser., s.v.

e- s,, .s

e. eaves s".E.,.

[ gsg

\ g asr s.ea.,

astea ri.A

'T

  • Au leakne inno he mondery ceamuned waadd kJUhred and reinenedpone k unnianon unt 4%r nngannpreum is edWend.

The releases are calculated from each E- 4+=2 with a separate TACT run. The results are aggregated using EXECL 5.0. EXCEL is not Qualir/ Software, therefore a hsting of the funcuons and formulas used are included for each spreadsheet in Appendix A: EXCEL Spreadsheet Funcuons and Formulas.

6.3. Source Term Basis The source core activity was taken from a Stone and Webster calculation (Ref.17) used in the development of Table 15.0-7 in the FSAR (Ref.10), nanaissent with other MP3 FSAR analyses. The net release fractions are 100% of the core noble gases and 50% of the iodines. The timing of the release reflects the Timing Only RST proposal, such that at t=30 secs the gap activity (5% noble gas and iodines) is ia='=a*==2=ly released and at t=30 mins the remaintier of the activity, the "early in vessel" release, (95% of the core noble gas and 45% of the iodines) is Jnerantaneously released. This is w ,4=wi to the earlier Reg. Guide 1.4 (Ref. 3) source term below in Table 1.

~_ ._mm.._

)

\

SUBJECT EAB and LPZ Doses DWM/WJE 3/20/96 from a MILLSTONE ,,,_, CH.GD a  !

UNIT 3 LOCA , 2A*,0 # M3LOCA94/ '1 - R3 Rev 1 SHEET 7 W 29 j Table 1 Reg. Gul le L4 vs. Timing Only Release Mb JM g 100 % 50 %

tecMMM 5% 5% {

. liid3MM 95% 45%  ;

W@Is 100 % 50 % 100 % 50 % l l 4

The iodtne form is 91% "= - ^ 1. 5% particula:c, and 4% organic as naarirwa in SRP 6.5.2, Rev. 2.

i 5.4. lodine Removalin Containment  ;

Credit is taken for ma'aiaa-at sprays in removing elemental and particulate lodme from the containment atmosphere The spray removal and wall plate-out rates for iodines were calculated (Ref. 20) by Stone and Webster (S&W) using SRP 6.5.2, Rev. 2 methods (Ref. 8). Credit is taken for plateout of elemental  !

lodme onto the wetted, unsprayed region of the containment (Ref. 20). The effectiveness of the sprays in I removing elemental iodine ends at the time when the maxunum allowed DF of 200 is reached (Ref. 8).  !

The effectiveness of the sprays in removing particulate iodine is reduced in accordance with SRP 6.5.2, Rev. 2 methods (by a factor of 10) when a particulate DF of 50 is achieved.

5.4.1. DF Defined for Multiple Time Release According to SRP 6.5.2 DF "...is defined as the maximum lodine concentration in the containment atma =h~e divided by the concentration ofiodine in the containment atmosphere at some time after decontamination" (time t=j). 1-131 is used as representative of all iodines since it has a long half-life (8.05 days).

DF I I*"'I *" "I*)( I~ )@I" forj>i j = (Elem. Iodine in Cont.)(% I-131) @ t = j For the Reg. Guide 1.4 source term maximum concentration occurs at t=0, the release of the entire source term. The RST Timing Only source term releases the iodine in two puffs, one at 30 sec and one at 30 min. To calculate conservative DF's the maximum concentration is taken as the sum of the concentration at t=30 see from the gap release plus the concentration component at t=30 min only from the "early in-vessel" release. Thus:

DFj = (5% I-131 @ t = 30 secs)+ (45% I-131 decayed to t = 30 mins)

(Elem. Iodine in Cont.)(% I-131) @ t = j This .ww.ch neglects the decay of the gap release that occurs for the first 30 min. By c=Wlating the DF in this fashion we are effectively maximizing the numerator Fct a fixed DF (either 200 or 50) the denominatar is also mavi=lud This means that the maximus allowed DF is reached with the highest value ofiodme in containmant, i.e., earlier in the acquence. This is consenative in that credit for sprays is lessened by reducing / stopping the removal ofiodine by the sprays earlier in the sequence. This is very conservative with respect to the philosophy of SRP 6.5.2, which limits credit for iodine removal by sprays to observed physics. However, for a pilot plant initial application the results of this more conservative approach allow insights into the RST Timing Only proposal.

The calculation of the critical DF values of 200 and 50 is done by iterating with TACT. Only the final run of each series, showing the calculated DF, is included in this package.

1 SUBJECT EAB and LPZ Doses BY JShr/WJE DATE 3/20/96 from a MILLSTONE CHKED DATE UNIT 3 LOCA CALC # M3LOCA94/ 01048 - R3 Rev 1

, SHEET 8 OF 29 5.5. Dose Conversion Factors The thyroid dose conversion factors (DCF's) currently used in the TACT III code date back to ICRP 2 -

(1959), (Ref. 4 & 5). ICRP 30 (Ref. 7) adult thyroid DCF's will be used in this analysis because they are more up-to< late and reahstic. The TACT III results were adjusted using Excel 5 to derive the results with

, mCP 30 DCF's,

6. Analysis

i 6.1. Time une Table 2 is a timeline of significant events It is ine-led to serve as a guide in putting the thne component releases in perspective and showing the interdependence of each.

, 0.2. Assumptions Listed in Table 3 through Table 7 are the assumptions used in this calculation. Some of the assumptions warrant more detailed discussion and are described further in subsequent sections.

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f SUBJECT EAB and LPZ Doses BY DWM/WJE DATE 3hJe5,, _

from a MILLSTONE CHKED DATE _ , . _,,

UNIT 3 LOCA CALC # M3LOCA94/ 01048 - R3 Rev 1 SHEET 10 OF 29 Table 3 Gameral Assumptions - Apply to All Cases i

Power Level MWthermaf3G l@ 47 Ref.17. pg. 2 Core inventory gtWznm?%:n5%$g%;

L E __ ~ "Ivit Ref.17, pg.15 Core Release Fractions: $ .

k Timing only l'ST Proposal t = 30 sec ... Aoble loitinessg t = 30 min 96%*hoble' ghgases;45%Wilns!

,Ys d lodine Chemical Form: NMa  % %%4&a' y@':',t5y p' Ref. 3, pg.1.4-1

@':l:$'i',',DPick>

m ,

~~~m;'; ,wn sq,:w i>,r m ,p]

particulate ' " >

,; :,, <3,,~?

. s, ,q orgenic y,;i,y J > '+ 6 j',.< +g p Jff : A*%' " '

,)A> . + ',4 20.6Huti$y'*'M'N. 4,',*

Containment Leak Rate (L) p 5 m y' q r -

ep>:, '

,'m+,

'M cPTSCR "'* #3-25-95, Ref. 21 Enclosure building

,O':. u l'?

a +' Cf.

  • 30, s,plen c 4 n , , 'v ' e"'9 PTSCR #3-25-95, Ref. 21 drawdown *- &: >v ,

4y. , ,g . ,. . s . . . >r ,'<,, , . ,, . s . . .~. n ,vz . '.' .m .s s '/ v,,

Y$f f/ $$=**},', 5<- >'% 'lff f (F *%'

t

' Ref 3, pg.1.4-2 Offsite Breathing Rates: >

(04) hr ! , 3.47E-4 (m'/sec)

(6-24) hr i < 1J5E-4 ,

< /

'" q*

(24-720) hr 3a, 2.32E-4x L "^h

,,.;e.,> ,', ;;n <y 0,f'

,s

,e

'wy, n g6> ,,

i 4, i , :-f ', : ?,n ',, '<sv v LPZ X/Q's: ' '

3 ~; ',yp d Ref. 2, pg. 5 (04) hr (8-24) hr I ,, A9E 5, W' }y't:"3191Es(sech6 'Qifc4j

3',' ' 1 t f > 'q o' g (24-96) hr M'8.66E4 (96-720) hr $*!l2.63E4 l' ' ,"'y,,' ,

4,

,',,/

,y k ,ta:  : ' 'i Lb - , , , , ,

Dose Conversion Factors (4see Table 12)'g' ,' 1'/' c/ c ' ICRP30, Ref. 7 Table 4 Spray Assumptions- All Cases Pararneter < Value .

Basis Criticallodine DF values j

Max elementalgi% DF gNpJ@g$in '8 Ref 8, pg. 6.5.2-12 Crit particulate DF l$0@$$g$$

M

$yj %fWg Spray initiation Qgg&gg sesRg Ref.10,6.5.2.2, pg. 6.54 Quench vntenq Recirculation :secn e d pg. 6.2-48 LP.tainment Volumes 3 Free AirVolume Ref. 2, pg. 4 l.i.:iS5E6'16MMj.p..-

g: y ' ' - - --

Spray Region (Node 1) gy' .s e Ji Quench only $1;17E6Ms 5 Ref.19, pg.15 Quench + Racirc $$2E6fd /

Unsprayed Regn (Node 2) &d$5EE h [q

  • Quench only h18E6g.

$Ejggg i Quench + Recirr #s M gfp e ,; -

P 1 Sie h gate $fD J

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.-- ,+, u,.p .. .,,94.,e-.+.. . . . .3 . . .

m. a .wm. . - --.w - - - . . . -

SUBJECT EAB and LPZ Doces BY DWM/WJE DATE 3/20/96 from a MITLSTONE CHKED DATE UNIT 3 LOCA CALC # M3LOCA94/ 01048 - R3 Rev 1 SHEET 11 OF 29 Mixing rates: ^

Ref.19, pg. 25 (0 -400 sec) ' p(1/t l, if)' ;' ', r, ; '[

(400 -780 sec) , .93 - 4: ':,'5 ?

(780 -4100 sec) .98'F;,'ll$

(4100 -4680 sec) 46 y , O '4 :]

(4680 - 8000 sec) >'7 40 5', ' ' dd

(> 6000 sec) 2 00's - ;';'"[]

u z'.' ,;,::::.,:,, .

Elem. lodine Removal Coeff.: py,y'jfp/jf',^fj$ Ref. 8.pg. 6.5.212 & Ref. 20, Sprayed Region (Node 1) 3 9g A !k'Wl"g;g:jpg.29 ;4 ,'M 1m /$f N

'h' J Unsprayed Regn (Node 2)

Anemt k'l :$

w n::, .  ::~ a', ? %

Part. lodine Removal Coeff.: "% J~ ' ' d'q, Ref. 8,pg. 6.5.2-12 & Ref. 20 pg.

s During Quench spray # d -

[z 28 x o,4s e, w!%2.6/br ^ ,' o1 -

During Quench + Recirc '::27.'4/hr

^ ' ' ': a -

Accoe 72.74/hr ' '

Amt , ,

Table 5 Bypass Case Assumptions Pararneter . Value .

Bases .

i Bypass Release Rate BE.,;g;Jg Jfnfggll$5 Ref.10 Table 15.6-9, and (0-0.8) hr &6$%Msyjkg6 jig;#ywg Proposed Tech. Spec. PTSCR I (0.5-24) hr ,0278%1dapf ~ i #3-25-95, Ref. 21 pg. 3/4 6-2; l (24-720) hr 0.0139%f/dayy M "t i]w A ,, . Jasa s# <

Ref. 3, item C.1.e Bypass Leakage Fraction 0 9 Ref.10 Table 15.6-9 and I k .0427 % $

5

. ".< Ref.15, pg. 3/4 6-2 W s ' ' #,hiourid),gl  %~ ~.

Ref. pg.15.6-23 10,15.6.5.4, Releass Point 16istintheN}

EAB X/Q's: veur:;a;rakaNusmd (0-2) hr N@!!? DOM %iR Y@d Ref.2,pg.5 4isech0DIENik$

Table 6 Filtered Case Assumptions Paratneter Value

  • Basss .

Filtered Release Rate L g,g. Jogg.qg Ref.10 Table 15.6-9 and Ref. 21, (0.5-24) hr L pg. 3/4 6-2;

$2222%%,k?QM@FQ (24-720) hr HL3111%'/dayL s 7 Ref.3, item C.1.e n G sanen.gM aM 1 Fitter Efficiency $y$6sisliisnss;xN Ref. 2, pg. 4 i g 2 Release Point pM;pggscsgp$pgg'A L is6(ih Ref.10,15.6.5.4,pg.15l

""~

m g EAB X/Q's: @@

paa$ . ' "$ggd Ref. 2, pg. 5 i (0-2) hr M20Ei4 6*W I

l j SUBJECT EAB and LPZ Doses BY DWM/WJE DATE 3/20/96 )

j from a MILLSTONE CHKED DATE )

. UNIT 3 LOCA CALC # M3LOCA94/ 01048 - R3 R' L i SHEET 12 OF 29 1

I ,

1 Table 7 ESF Case Assumptions j t i Passineter l Value .

Liitsts '

Core inventory into sump: I@?Ap% noble gas, a<f t!, .M Ref.11 pg.15.6.5-16 l

~ '

., A and Ref. 3

h. ,, ,,>wJ- 60%

iodines s,k.c v,' : , :s, ,w s ,

, , ,w s ut

] Sump volume: ,

^;s< , ",,;f ? t u ,n/ ' ~ l, j Ref. 2, pg. 5 s i 220 sec -1 hr g 40000 (gal)x . ', f , ,

a 1 hr - 2 hr 4,700000 s;'A /: ~

-  % J

>2 hr 5000000@)@;<j'W',:;,'] ' '

lodine released from sump  ::r e sw,x '; .";'~kg;n , Ref. 2 and Ref.11
water $@057,.PW,I$,
, e
  • p; E a :c m'; 1' s

ESF leakage * ~:'y?.:

,MU Wk'M

' /'

s

y' ';:,;i; A:ar"";;"N;:l;"~;";;";y<5 Ref. 2, pg. 6

twice the max ,$p h h [ N [&

1 operational /.x f;J' f *'j'j'O o p," : u g ~

leakage 'w y ;;,y/

"a ; - l,b -:, / '; . 3 . ';

i Release Point wentilation ver'it . 'q',7 -

-! Ref.10,9.4.3.2,pg.

,,, 9.4-17

, r, , 1 ESF leakage begins Y ', 220 sed' ) ' 1( ' , Ref. 2, pg. 4 EAB X/Q's: )' ^'I " ' ' '

,  ?: Ref. 2, pg. 5 s

' i (0-2) hr 4.30E.4 (sec/m3 ' <>' <

6.3. Containment Volumes, Mixing, and Sprays l 6.3.1. Conta~nment Volumes i This calculation requires the volumes of the sprayed region (node 1) and the volume of the unsprayed l region (node 2) of containment. It should be noted that the volume of the sprayed and unsprayed regions changes when the sprays change from no spray, to quench only, to quench plus reef rculation sprays. This

, isillustratedin Table 4 and Table 8.

Table 8 All Cases: Spray Volumes, Mixing and Filter Rates as a Function of Time D.018' ,111 : 1,183,800 1,166,200 2.00 0. 39460 0. O.

$(1/J167/ 1,183,800 1,166,200 9.93

  • 195919

< ,2167 ;',5 834,140 1,515,838 13.98 194355

' 6 t139 '

+

6.222 3.604 6.550

, 1.139-1.272 *

  • 7.46 103711 1.272 1.667

'1.067* 24 2.00 27805

' ' > 24 ' : 3.111 1.802 3.275 6.3.2. Mixing and Spray Effectiveness Credit is taken for *=tae prayss in removing elemental iodine from the containment atmosphere.

The quench sprays become effective within 64 seconds (Ref.10) and the recirculation spray does not

._ . . . . . ... .. .. ...,_. ..-. .. -.,_.-.s,,.. ., .. .. ..

9ECT EAB and LPZ Doses BY DWM/WJE DATE 3/20/96 from a MILLSTONE CHKED DATE UNIT 3 LOCA CALC # M3LOCA94/' 01048 - R3 Rev 1 SHEET 13 OF 29 initiate until 780 =acands (Ref.10 and 19). The effectiveness of the sprays in removing elemental iodine

ends at the time when the ==d== allowed DF is reached (Ref. 8). The maximum allowed DF for elemental iodine is 200 when either the quench or recirculation sprays operate ladaaaadantly or together (Ref 8).

During spray system operation, raa*=inment mixing occurs between the sprayed region and the unsprayed region. The mixing rate varies with time from 2 turnovers of the unsprayed volume region per hour up to 14 turnovers per hour (Ref.19) as shown in Table 8. The mixing rate between the unsprayed to sprayed regionsis calculated as follows:

Mixing Rate a (Unsprayed volume) x (turnover rate)

The 81tered transfer rate from the sprayed and unspr=wd regions to the environment through nantainment 81tration leakage are calculated by taking the volume of each . Won multiplied by the Sitered leak rate.

For example, following 30 minntas when the enclosure building taomes subst=^=aheric,0.6222% of the nnntninment leakage per day (0.65% 0.0278%) will be Altered prio to release to the environment. Thirty minutes following the LOCA the sprayed region with quench and rect;c sprays operating will be 1,515,858 cubic feet. Therefore the Sprayed Filter Rate following 30 muutes is calculated as follows:

S Sprayed Filter Rateoo 2% = (1,515,858 A )(.6222%fday)

= 6.550E+00 A'/ min At 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> into the event the release rates decrease to one half their origina value (Ref. 3), therefore:

Sprayed Filter Rate (>24 hr) = (6.550E+00 R3/ min)(0.5)  !

= 3.275E@0 A 3/ min l Table 8 above lists some major time '+-:- h t vanables related to sprays and volumes and the related mixing rates and filter rates.

The spray removal and wall plate-out rates for elemental iodines were calculated by Stone and Webster .

(S& W) using SRP 6.5.2, Rev. 2 methods (Ref. 9). The maximum allowed spray removal rate defined in SRP t>.5.2, Rev. 2 is 20&. S&W calculated an elemental wall plate-out removal rate within the quench spray region of 5.1/hr and a spray removal rate of 20.0/hr for a total of 25.1/hr (Ref. 20). An elemental wall plate-out removal rate within the unsprayed region was calculated to be 1.2/hr up to 30 minutes I following the LOCA, until the containment walls no longer behave as a heat sink (Ref. 20).

For partimlate iodine S&W calculated an initial quench spray removal rate for particulate iodme of 12.6/hr (Ref. 20). Once recire, sprays haname effective, at 780 seconds, the particulate iodine removal rate increases to 27.4/hr (Ref. 20). As specified in SRP 6.5.2, Rev. 2 this rate decreases to one tenth of the ,

l total removal or 2.74/hr once the m==*adad aerosol mass of particulate iodine is depleted by a factor of

. 50. The time that occurs is diamanad in " Time to Achieve Particulate Iodine Depletion of 50" on page 16, 6.4. Releases Into Containment The source term is comprised of the magnitude, timing, and physical / chemical form of the radionuclide release from the fuel. nese were summarized in Section " Source Term Basis" on page 6. Even though its contribution is negligible, the coolant activity is included in this analysis for completeness ne normal raalant activity was taken from the FSAR Design Bases coolant activity Table 11.1-2 (Ref.

10). The magnitude of source core activity was taken from a Stone and Webster calculation 12179-RP-

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

l SUBJECT EAB and LPZ Doses BY DWM/WJE DATE 3/30/96 from a MILLSTONE CHKED DATE UNIT 3 LOCA CALC # M3LOCA94/ 01048 - R3 Rev 1 SHEET 14 OF 29 4 194-0 (Ref.17) which is the bases for FSAR Table 15.0-7 (Ref.10). Table 9 lists the individual release i

activities for each release case taking into account the assumed release fracticas and timing

, considerations.

Table 9 Release Activities M2 Release 0seqond 30 second 30 mo Fractnon Cooliant rel. Gap selease Fuel r ' . -

tru m # 0 H (Ch. (Cr) (C M31 2.6E+00 9.11E+07 0.05 0.45 S.10E+02 4.56E+06 4.10E+07 M3@&.2 9.3E-01 4.2E+00 1.30E+08 0.05 0.45 2.18E+02 6.50E+06 5.85E+07 2.04E+08 0.05 0.45 9.85E+02 1.02E+07 9.18E+G7 in33} a% d M341 5.8E-01 2.38E+08 0.05 0.45 1.36E+02 1.19E+07 1.07E+08 M3N! $ 2.2E+00 1.88E+08 0.05 0.45 5.16E+02 9.40E+06 8.46E+07 m g M$hih, 4.5E-01 1.58E+07 0.05 0.95 1.06E+02 7.90E+05 1.50E+07 Xr-88dhi 1.7E+00 3.96E+07 0.05 0.95 3.99E+02 1.98E+06 3.76E+07 3.4E-02 8.83E+05 0.05 0.95 7.97E+00 4.42E+04 8.39E+05 X688PMdl NfMs 1.2E+00 7.71E+07 0.05 0.95 2.81E+02 3.86E+06 7.32E+07 Il 3.4E+00 1.08E+08 0.05 0.95 7.97E+02 5.40E+06 1.03E+08

@.48]j

@h j 1.1 E-01 1.40E+08 0.05 0.95 2.58E+01 7.00E+06 1.33E+08 Xe-131,my 1.1E 02 8.01E+04 0.05 0.95 2.58E+00 4.01E+03 7.61E+04 Xed33m1 6.1E-01 4.89E+06 0.05 0.95 1.43E+02 2.45E+05 4.65E+06 2.6E+01 2.03E+08 0.05 0.95 6.10E+03 1.02E+07 1.93E+08 XeQ33@3 Nes136m 1.2E+00 5.50E+07 0.05 0.95 2.81E+02 2.75E+06 5.23E+07 Xo-1381, 5.1E+00 5.38E+07 0.05 0.95 1.20E+03 2.69E+06 5.11E+07 Xt.137L 1.7E-01 1.83E+08 0.05 0.95 3.99E+01 9.15E+06 1.74E+08 Xe-133r M 6.0E-01 1.80E+08 0.05 0.95 1.41E+02 9.00E+06 1.71E+08 Because TACT III was run as a two node calculation (sprayed and unsprayed regions) the fraction of release into each node was calculated. The activity released from the mre is assumed to be released i instantaneously and be equally distributed throughout the containment atmosphere. At any release time, l the activity is proportionally distributed in each node. Table 10 lists the calculated node fractions for the i sprayed and unsprayed regions based on the volumes in each region. Prior to 780 seconds only the )

quench sprays are in use, aAer 780 seconds the sprayed volume increases due to both quench and recire.

sprays in use.

Table 10 Sprayed and Unsprayed Node Fractions

. :o .: ._ so  ::

2.35E+03 2.35E+06 - -

otalcent.,d 1.17E+06 1.52E+06 0.496 0.645 if)ldf&

YW91 1.18E+06 8.34E+05 0.504 0.355 The TACT III code requires the source to be broken down by the node into which it is released. Table 11 lists the activity in each node that is assumed to be instantaneously released and equally distnhited into contatament. These values were obtained by multiplying the total release activities as listed in Table 9 by the node fraction for that time step in Table 10.

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

J i SUBJECT EAB ono ,* .

c BY DWM/WJE DATE 3/20/96 from a MIL', - ..E CHKED DATE j UNIT 3 LOA CALC # M3LOCA94/ 01048 -R3 Rev 1 l, SHEET 15 OF 29 Table 11 Isotopic Releases by Node i i .- i i. - i i 1.86We n 3.03E+02 3.07E+02 2.26E+06 2.29E+06 2.64E+07 1.46E+07 ,

l l 4.89E+02 4.96E+02 5.06E+06 5.14E+06 5.92E+07 3.26E+07 1 i332 "i34 "1 6 75E+01

. 6.85E+01 5.91E+06 5.99E+06 6.91E+07 3.80E+07

! 4.66E+06 4.74E+06 5.46E*17 3.00E+07

.$ikkh. 2.56E+02 2.60E+02 i m it m e j ~ "44iiWM/ 5.24E+01 5.32E+01 3.92E+05 3.98E+05 9.68E+06 5.33E+06 j 9.83E+05 9.97E+05 2.43E+07 1.34E+07 MP 1.98E+02 2.01 E+02 ]

l 2 3.96E+00 4.02E+00 2.19E+04 2.22E+04 5.41E+05 2.98E+05 l j 4_7 . . 1.40E+02 1.42E+02 1.91E+06 1.94E+06 4.72E+07 2.60E+07 i Mif 3.96E+02 4.02E+02 2.68E+06 2.72E+06 6.62E+07 3.64E+07

! ]M J 1.28E+01 1.30E+01 3.47E+06 3.53E+06 8.58E+07 4.72E+07 l 1.28E+00 1.30E+00 1.99E+03 2.02E+03 4.91 E+04 2.70E+04

..lja Me-133 @ini 7.10E+017.21 E+01 1.21E+05 1.23E+05 3.00E+06 1.65E+06

{ .Mi33l[ 3.03E+03 3.07E+03 5.04E+06 5.11E+06 1.24E+08 6.85E+07 l MN 1.40E+02 1.42E+02 1.36E+06 1.39E+06 3.37E+07 1.85E+07 j M36? 5.93E+02 6.02E+02 1.33E+06 1.36E+06 3.30E+07 1.81E+07 2.01E+01 4.54E+06 4.61E+06 1.12E+08 6.17E+07 l

l M,S45slE fj$7b6.98E+011.98E+017.09E+01 4.47E+06 4.53E+06 1.10E+08 6.07E+07 i

! 6.5. Decontamination Factors l

l TACT III was used iteratively to determine when the maximum allowed elemental iodine DF of 200 for spray effectiveness would be achieved. The same process was used to determine when particulate iodine would be depleted by a factor of 50 so as to adjust the particulate removal rate as specified in SRP 6.5.2, Rev. 2. To determine the respective DF's, the maximum concentration of elemental and particulate I 131 1 in containment must first be calculated. As di= "M above, to conservatively accomplish this the curies

ofI-131 released into containment at each source timing stage were determined and summed to obtain an l effective " maximum" concentration.
a << a .< u ... a ..

l a .

i 3: ' 4 Mar.18,1996

! sec" i jobf03161 2.243E+03 1.232E+02 24.75 5.551E+02 3.049E+01 l . rl1;j Mar.18,1996

sec ; Job #03161 3.863E+07 2.122E+06 10.72 4.141E+06 2.275E+05 i 4 L >,'j Mar.18,1996 i min j job #03154 3.040E+08 1.670E+07 12.25 3.724E+07 2.046E+06 j y 4 l ctal[d 4.138E+07 2.273E+06 i

f 1

i

_ _ ____ _ g - ._ _

..,, s

, 7 i4 SUBJE." 9 anTZ Dose _s _ BY DWM/WJE DATE 3/20/96 i

_um a MILLSTONE CHKED DATE l UNIT 3 LOCA CALC # M3LOCA94/ 01048 - R3 Rev 1 SHEET 16 OF 29

) 6.5.1. Time to Achieve Maximum ElementalIodine Spray DF=200 j TACT III run dated Mar.18,1996, job #03129 is the final run in an iterative sequence which calculates the following results:

i i ~1 Riemental M3103

  • Initial
  • 4.138E+7 curies

~

- ,tentalNMil:WF.

Blag .

,.3 3686 sec 1.497E+6 curies

MMISMM . (1.024 hr)

I j DF = (4.138E+7) / (1.497E+6 Ci)(13.89%)

DF wes., = 199.1 1 6.5.2. Time to Achieve Particulate Iodine Depletion of 50

TACT III was run to deternune at what time is the =_iW aerosol mass of particulate iodme depleted i by a factor of 50. Camaa*~ run dated Mar. 18,1996, job 03129, calculates the following results:

g Comp < ment At Isme t= Result

! Sinitigl*9! articulate 4131, f!

  • Initial
  • 2.273E+6 curies 1 Sbleiflesticule$s40 dine ' j 3094 sec 3.404E+5 curies 4

$tetent of M31 J ' ' '6 3094 sec 13.40%

's, M <t (0.8595 hr)

} therefore, DF = (2.273E+6) / (3.404E+5 Ci)(13.40%)

DF m., = 49.8 2

Therefore, as specified in SRP 6.5.2, Rev. 2, at 3094 seconds the removal rate of particulate lodme is j decreased from 27.4/hr to 2.74/hr.

6.5.3. Containment Bypass Leakage Bypass I entrare is defined by the NRC (Ref.14) "as that leakage from the primary containment which can

circumvent the secondary containment boundary and escape directly to the environment, i.e., bypasses the leakage collection and filtration systems of the secondary containment". Bypass leakage at a rate of 0.65Wday is maanmM starting at t=0 and continuing at that rate until the enclosure buildmg achieves subatma=h~ic conditions at 0.25" water at t=30 minutes. Once substmospheric, the aux 1hary building filtration system will handle the majority of the containment leakage. Tech. Specs define a bypass fraction of 0.0421,(Ref.15) upon subatmospheric moditions. The FSAR lists the bypass fraction as l 0.042771 (Ref.10). Because it is more conservative, i.e., calculated doses using 0.04277 will exceed

, those from Tech. Spec. conditions, the FSAR value was used in this analysis, increasing the unfiltered i ground release portion of the 0.65Wday release After 30 minutes the bypass leakage decreases to a rate

of 0.0278Wday, it will continue at that rate until 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following the LOCA where the leakage is j decreased by one half to 0.0139Wday as MnM by Reg. Guide 1.4 (Ref. 3). The ==>mations used to 3

calculate the containment bypass leakage portion of the LOCA dose are listed in Table 5.

. 6.5.4. Containment Filtered Leakage Caa'ainmaat Eltered leakage consists of activity filtered by the auxiliary building filter due to containment leakage and released from the turbine building ventilation vent. Filtered containmeu leakage begins at t=30 minutes at a rate of 0.6222Wday when the enclosure building achieves a negative pressure of 0.25"

, water. It will continue at that rate until 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following the LOCA where the leakage is decreased by 1

i

SUBJECT EAB and LPZ Doses BY.i. - DWM/WJE DATE 3/20/96 from a MILLSTONE CHKED DATE l UNIT 3 LOCA CALC # M3LOCA94/ ' 01048 - R3 Rev 1 SHEET 17 OF 29 l

j one half to 0.311IWday as defined by Reg. Guide 1.4 (Ref. 3). The assumptions used to calculate the containnwnt filtered leakage portion of the LOCA dose are listed in Table 6.

j 6.5.5. ESF Leakage j Following a LOCA, long term cooling is provided through the use of ESF equipment. Much of this t

equipment exists outside of the primary cantainnwnt and presents a potential source for leakage when j water is pumped from the mania =*=' sump Fission products maniard in the sump water can bc l j relaami from the water into the ESF Building atmosphere ne source term for the ESF portion of the  !

. LOCA dose assumes no noble gases and all of the released core iodines (effectively 50%) are in the sump i water,10% of that quantity is released from the water into the enclosure building stav=nhare. Therefore, I i to obtain the iodine source term inventories, the values in Table 9 for the three stages ofielease (i.e.,

coolant activity at t=0, Gap activity at t=30 sec, and In-Vessel activity at t=30 min) were multiplied by 0.1 i

and released at their appropriate times. De assumptions used to calculate the ESF leakage portion of the LOCA dose are listed in Table 7.

l' 6.6. Leak Rate Discussion The enclosure bmlding becomes =durmaapheric achieving 0.25 inch water 30 minutes following a LOCA. Therefore up to 30 minutes, normal design leakage proposed at 0.65Wday will exist bypassmg

] secondary catmnment (auxihary bmidmg filtration). Following 30 minutes, when the enclosure building l hamaw edutmaspheric, a bypass fraction of 0.04277 (Ref.15) or bypass release rate of 0.0278%/ day is

.,, a l

l 6.7. Thytold Dose Conversion Factors The adjustment from TACT III to ICRP 30 thyroid DCF's was donc using the equation given below.

1 D=

% - D *%

  • F
  • R.

i i l where, 4

D" - nyroid dose for isotope i agiusted for ICRP 30 DCes.

I D *" = Total Dyroid dose from TACT III for isotope i

= Fraction of totaliodine.

! Fi

=

Ri Ratio ofICRP 30 to TACT 111 dose conversion factors (see Table 12).

Table 12 Dyroid Dose Conversion Factors 131 M's 1.49E+6 1.073E+6 0.718 32 1.43E+4 6.290E+3 0.440 l

35[W ^Vj 2.69E+5 1.813E+5 0.674 i 134 "?" l 3.73E+3 1.073E+3 0.288 i

M38  :' 5.60E+4 3.145E+4 0.562

! Note: 3.7E+12 used to convert from Sv/Bq to rem /Ci.

i

SUBJECT EAB and LPZ Doses CY DWi ~

+ 'IE 3/20/96 hom a MILLSTONE CHKED DATE UNIT 3 LOCA CALC # M3LOCab / 01048 - R3 Rev 1 SHEET 18 OF 29 6.8. Computer Codeinput Data Sets The input data sets to the TACT III (version 83.0) computer code are given in Table 13 through Table 15.

Table 13 Tact III Input Data Set - (Costalement Bypass Leakage)

Tac t illInput Data Set - (Contauunent Bypass Leakage)

MP3 LOCA (BYPASS) GAP RELEASE At 30 SEC AND IN-VESSEL AT 30 MINUTES 21522103189600 3636. 0.0 0.501.01.0 9.100E-01 4.000E-02 5.000E-02 1 20 0.000E-0 8.333E-03 2 22 3.030E+02 3.070E+02 2 23 1.080E+02 1.100E+02 2 24 4.890E+02 4.960E+02 2 25 6.750E+01 6.850E+01 2 26 2.560E+02 2.600E+02 2 29 5.240E+01 5.320E+01 2 2 10 1.980E+02 2.010E+02 2 2 11 3.960E+00 4.020E+00 2 2 12 1.400E+02 1.420E+02 2 2 13 3.960E+02 4.020E+02 2 2 14 1.200E+01 1.300E+01 2 2 15 1.280E+00 1.300E+00 2 2 16 7.100E+01 7.210E+01 2 2 11 3.030E+03 3.010E+03 2 2 18 1.400E+02 1.420E+02 2 2 19 5.930E+02 6.020E+02 2 2 20 1.980E+01 2.010E+01 2 2 21 6.900E+01 1.090E+01 3 20 1.166t+06 1.184E+06 1031 0.0 0.0 3.946E+04 1032 0.0 3.946E+04 0.0 1131 6.500E-01 0.0 0.0 11 3 2 6.500E-01 0.0 0.0 17 6 0 5.420E-04 2.910E-05 3.470E-04 0.0 0.0 6.500E-01 1 20 8.333E-03 1.778E-02 2 22 2.260E+06 2.290E+06 2 23 3.230E+06 3.270E+06 2 24 5.060E+06 5.140E+06 2 25 5.910E+06 5.990E+06 2 26 4.660E+06 4.740E+06 2 29 3.920E+05 3.980E+05 2 2 10 9.830E+05 9.970E+05 2 2 11 2.190E+04 2.220E+04 2 2 12 1.910E+06 1.940E+06 2 2 13 2.680E+06 2.720E+06 2 2 14 3.470E+06 3.530E+06 2 2 15 1. 990E+ 03 2.020E+03 2 2 16 1.210E+05 1.230E+05 2 2 11 5.040E+06 5.110E+06 2 2 18 1.360E+06 1.390E+06 2 2 19 1.330E+06 1.360E+06 2 2 20 4.540E+06 4.610E+06 2 2 21 4.470E+06 4.530E+06 1 20 1.778E-02 1.111E-01 5 20 2.510E+01 1.200E+00 1 20 1.260E+01 0.0 1 20 1.111E-01 2.167E-01 1031 0.0 0.0 1.959E+05 1032 0.0 1.959E+05 0.0 1 20 2.167E-01 5.000E-01 3 20 1.516E+06 8.341E+05 1 20 2.740E+01 0.0 1031 0.0 0.0 1.943E+05 1032 0.0 1.943E+05 0.0 1 20 5.000E-01 5.0002E-1

SUBJECT EAB and LPZ Doses BY DWM/WJE DATE ,.,/20/96 from a MILLSTONE ChKE DATE UNIT 3 LOCA CALC # M3LOCA94/ 01048 - R3 Rev 1 SHEET 19 OF 29 Tat t illInput Data Set - (Containment Bypass Leakage) 2 22 2.640E+07 1.460E+07 2 23 3.770E+07 2.080E+07 2 24 5.920E+07 3.260E+07 2 25 6.910E+07 3.800E+07 2 26 5.460E+01 3.000E+07 2 29 9.680E+06 5.330E+06 2 2 10 2.430E+07 1.340E+07 2 2 11 5.410E+05 2.980E+05 2 2 12 4.720E+07 2.600E+07 2 2 13 6.620E+07 3.640E+01 l 2 2 14 8.580E+07 4.720E+07 1

2 2 15 4.910E+04 2.700E+04

( 2 2 16 3.000E+06 1.650E+06 l 2 2 17 1.240E+08 6.850E+07 2 2 18 3.370E+01 1.850R+07 2 2 19 3.300E+01 1.8 UE+07 2 2 20 1.120E+08 6.170E+07 2 2 21 1.100E+08 6.070E+07 5 20 2.510E+01 0.0 11 3 1 2.780E-02 0.0 0.0 11 3 2 2.180E-02 0.0 0.0 l 17 6 0 5.420E-04 2.910E-05 3.470E-04 0.0 0.0 2.780E-02 1 20 5.0002E-1 8.595E-01 1 20 8.595E-01 1.024E+00 7 20 2.740E+00 0.0 1 20 1.024E+00 1.139E+00 5 20 0.0 0.0 1 20 1.139E+00 1.667E+00 1031 0.0 0.0 1.037E+05 1032 0.0 1.037E+05 0.0 1 20 1. 667 E+ 00 2.000E+00 1031 0.0 0.0 2.181E+04 1032 0.0 2.781E+04 0.0 1 20 2.000E+00 8.000E+00 17 60 0.0 2.910E-05 3.470E-04 0.0 0.0 2.180E-02 1 20 8.000E+00 2.400E+01 17 6 0 0.0 1.990E-05 1.750E-04 0.0 0.0 2.180E-02 1 20 2.400E+01 9.600E+01 11 3 1 1.390E-02 0.0 0.0 11 3 2 1.390E-02 0.0 0.0 17 6 0 0.0 0.660E-06 2.320E-04 0.0 0.0 1.390E-02 1 20 9.600E+01 7.200E+02 17 6 0 0.0 2.630E-06 2.320E-04 0.0 0.0 1.390E-02 O/

D Table 14 Tact HI laput Data Set -(Containment Filtered Imkage)

Tact fit input Data Set - (Containment Futtered Leakage)

MP3 LOCA (FILTERED) GAP RELEASE AT 30 SEC AND IN-VESSEL AT 30 MINUTES 2 15 2 21 03 18 96 0 0 3636. 0.0 0.50 1.0 1.0 9.100E-01 4.000E-02 5.000E-02 1 20 0.000E-0 8.333E-03 2 22 3.030E+02 3.010E+02 2 23 1.080E+02 1.100E+02 2 24 4.890E+02 4.960E+02 2 25 6.750E+01 6.850E+01 2 26 2.560E+02 2.600E+02 2 29 5.240E+01 5.320E+01 2 2 10 1.980E+02 2.010E+02 2 2 11 3.960E+00 4.020E+00 2 2 12 1.400E+02 1.420E+02 2 2 13 3.960E+02 4.020E+02 2 2 14 1.280E+01 1.300E+01

> 2 2 15 1.280E+00 1.300E+00 2 2 16 7.100E+01 7.210E+01 2 2 11 3.030E+03 3.070E+03 2 2 18 1.400E+02 1.420E+02

SUBJECT EAB and LPZ Doses BY DWM/WE DATE 3/20/96 ..

from a MILLSTONE CHKED DATE UNIT 3 LOCA CALC # M3LOCA94/- 01048 - R3 Rev 1 SHEET 20 OF 29 e Tact IllInput' Data Set - (Contain nent Foltered Leakage) 2 2 19 5.930E+02 6.020E+02 2 2 20 1.980E+01 2.010E+01 2 2 21 6.980E+01 7.090E+01 3 20 1.166E+06 1.184E+06 1031 0.0 0.0 3.946E+04 1032 0.0 3.946E+04 0.0 17 6 0 4.300E-04 2.910E-05 3.470E-04 0.0 0.0 0.000E-00 1 20 8.333E-03 1.778E-02 2 22 2.260E+06 2.290E+06 2 23 3.230E+06 3.270E+06 2 24 5.060E+06 5.140E+06 2 25 5.910E+06 5.990E+06 2 26 4.660E+06 4.740E+06 2 29 3.920E+05 3.980E+05 2 2 10 9.830E+05 9.970E+05 2 2 11 2.190E+04 2.220E+04 2 2 12 1.910E+06 1. 94 0E+06 2 2 13 2.680E+06 2.720E+06 2 2 14 3.470E+06 3.530E+06 2 2 15 1. 990E+ 03 2.020E+03 2 2 16 1. 210E+ 05 1.230E+05 2 2 17 5.040E+06 5.110E+06 2 2 18 1.360E+06 1.390E+06 2 2 19 1.330E+06 1.360E+06 2 2 20 4.540E+06 4.610E+06 2 2 21 4.470E+06 4.530E+06 1 20 1.718E-02 1.111E-01 5 20 2.510E+01 1.200E+00 7 20 1.260E+01 0.0 1 20 1.111E-01 2.167E-01 1031 0.0 0.0 1.959E+05 1032 0.0 1.959E+05 0.0 1 20 2.167E-01 5.000E-01 3 20 1.516E+06 8.341E+05 1 20 2.740E+01 0.0 1031 0.0 0.0 1.943E+05 1032 0.0 1.943E+05 0.0 1 20 5.000E-01 5.0002E-1 2 22 2.640E+07 1.460E+07 2 23 3.770E+07 2.080E+07 2 24 5.920E+07 3.260E+07 2 25 6.910E+07 3.800E+07 2 26 5.460E+07 3.000E+07 2 29 9.680E+06 5.330E+06 2 2 10 2.430E+07 1.340E+07 2 2 11 5.410E+05 2.980E+05 2 2 12 4.720E+07 2.600E+07 2 2 13 6.620E+07 3.640E+07 2 2 14 8.500E+07 4.720E+07 2 2 15 4. 910E+04 2.700E+04 2 2 16 3.000E+06 1.650E+06 2 2 17 1.240E+08 6.850E+07 2 2 18 3.370E+07 1.850E+07 2 2 19 3.300E+07 1.810E+07 2 2 20 1.120E+08 6.170E+07 2 2 21 1.100E+08 6.070E+07 5 20 2.510E+01 0.0 1031 6.550E+00 0.0 1.943E+05 1032 3.604E+00 1.943E+05 0.0 1231 9.500E+01 0.0 0.0 12 3 2 9.500E+01 0.0 0.0 1331 9.500E+01 0.0 0.0 1332 9.500E+01 0.0 0.0 14 3 1 9.500E+01 0.0 0.0 14 3 2 9.500E+01 0.0 0.0 17 6 0 4.300E-04 2.910E-05 3.470E-04 0.0 0.0 6.222E-01 1 20 5.0002E-1 8.595E-01 1 20 8.595E-01 1.024E+00 7 20 2.740E+00 0.0 1 20 1.024E+00 1.139E+00

. . 4 .. .

. _ _ _ _-._____m _ . . . _ . .

1 l

l SUBJECT EAB and LPZ Doses BY DWM/WJE DATE 2A0/96 l from a MILLSTONE CHKED DATE UNrr 3 LOCA CALC # M3LOCA94/ 01048 - R3 Rev 1 SHEET 21 OF 29 .

l Tact HIItuput Data set - (Contatnment Fsttered Leakage) 5 20 0.0 0.0 1 20 1.139E+00 1.667E+00 1031 6.550E+00 0.0 1.037E+05 1032 3.604E+00 1.037E+05 0.0 1 20 1.667t+00 2.000E+00 1031 6.550E+00 0.0 2.181E+04 1032 3.604E+00 2.781E+04 0.0 1 20 2.000E+00 8.000E+00 17 6 0 0.0 2.910L-05 3.470E-04 0.0 0.0 6.222E-01 1 20 8.000E+00 2.400E+01 17 6 0 0.0 1.990E-05 1.150E-04 0.0 0.0 6.222E-01 1 20 2.400E+01 9.600E+01 1031 3.275E+00 0.0 2.781E+04 1032 1.802E+00 2.181E+04 0.0 11 6 0 0.0 8.660E-06 2.320E-04 0.0 0.0 3.111E-01 1 20 9.600E+01 1.200E+02 11 6 0 0.0 2.630E-06 2.320E-04 0.0 0.0 3.111E-01 0/

O Table 15 Tact IB Impet Data Set -(ESF I sakage)

Tact HIInput Data Set - (ESF Leakage)

MP3 LOCA (ESF) GAP RELEASE AT 30 SEC AND IN-VESSEL AT 30 MINUTES 1 10 2 8 02 20 96 0 0 3636. 0.0 0.05 0.0 0.0 9.100E-01 4.000E-02 5.000E-02 1 20 0.000E-0 8.333E-03 i

2 12 6.100E+01 2 13 2.180E+01 l 2 14 9.850E+01 l 2 15 1.360E+01 i i 2 16 5.160E+01 1 3 10 1.069E+04 l 17 6 0 4.300E-04 2.910E-05 3.410E-04 0.0 0.0 0.0 1 20 8.333E-03 6.110E-02 2 12 4.560E+05 2 13 6.500E+05 2 14 1.020E+06 2 15 1.190E+06 4 l

2 16 9.400E+05 1 20 6.110E-02 5.000E-01 1021 5.886E-03 0.0 1211 9.500E+01 1311 9.500E+01 14 1 1 9.500E+01 1 20 5.000E-01 5.0002E-1 2 12 4.100E+06 2 13 5.850E+06 2 14 9.180E+06 l 2 15 1.070E+07 1 2 16 8.460E+06 l 1 20 5.0002E-1 1.000E+00 I i 1 20 1.000E+00 2.000E+00 3 10 9.357F+04 1 20 2.000E+00 8.000E+00 3 10 1.337E+05 17 6 0 0.0 2.910E-05 3.470E-04 0.0 0.0 0.0 1 20 8.000E+00 2.400E+01 11 6 0 0.0 1.990E-05 1.750E-04 0.0 0.0 0.0 1 20 2.400E+01 9.600E+01 11 6 0 0.0 8.660E-06 2.320E-04 0.0 0.0 0.0 1 20 9.600E+01 7.200E+02 17 6 0 0.0 2.630E-Of 2.320E-04 0.0 0.0 0.0 0/

7 SUBJECT EAB and LPZ Doses BY DWM/WJE DATE 3/20/96 from a M11.1RTONE CHKED DATE UNIT 3 LOCA CALC # M3LOCA94/, 01048 - R3 Rev 1 j

SHEET 22 OF 29 6.9. ResuNs of ComputerRuns y '

Using the assumptions described within this A-?= ==t, each component of the LOCA dose was run using TACT III. The TACT III input data sets in Section 6.8 were run on the Wethersfield IBM 3090 l mainframe wmputer. The dose components were munnwt to obtain total Millstone EAB and LPZ doses as a result of a MP3 LOCA. The thyroid doses adjusted for ICRP 30 DCF's in each time interval are listed inTable 16 through Table 18 with corr *=anding data. The summary of both thyroid and whole

, body dose results appear in Table 19 and Tabic 20. The matainment bypass leakage TACT III results are l given in c =;-iter outputjob number 03129, Mar.18,1996. Tbc containnwnt filtered leakage TACT III l results are given in c ==;-ser outputjob number 03140, Mar,18,1996. The ESFleakage TACTIII l results are given in man =dar outputjob number 05104, Feb. 26,1996.

)

l l

l l

l l

l t

i l

i 1

l l

B l

. - . . . ...,..m. . . , , _

i

. 1 SUBECT EAB and LPZ Doses BY DWM/WJE DATE 3/20/96 from a MILLSTONE CHKED DATE UNIT 3 LOCA CALC # M3LOCA94/ 01048 - R3 Rev 1 SHEET 23 OF 29 Table 16 ICRP 30 Hyroid Dose Adjustment (Costala=*=t Bypass I sahage)

DCF R.stw 0.718 0.440 0 674 0.268 0.582 g003Q.000333i ; 7.534E41 2.581E43 2.196E41 4.191 E-04 2.394E 02 7.0366E-Of i i" 5 6.057E-01 9.001E-03 2.893E 01 4.313E43 5.162E-02 6.9373E-Of 6.882E-01 8.974E43 2.092E41 4.163E-03 5.145E 02 6.9383E-01 e '

6.673E 01 8.730E 03 2.800E 01 3.657E-03 5.106E-02 6.94086-Of 87i .

E893E-01 8.356E-03 2.685E 01 3.415E43 5.040E-02 6.945fE-01 3

31,034[k 6.733E-01 7.704E43 2.671E 01 2.72CE 03 4.909E-02 6.9522E-Of 6.773E 01 6.968E-03 2.000E 01 2.063E 03 4.766E-02 6.9603E-Of it:;1.0137t:139 6.789E41 6.685E 03 2.865E-01 1.830E 03 4.706E 02 6.9633E-of ML1397L887h;p 3 6.823E 01 6.119E 03 2.643E 01 1.444E 03 4.583E 02 6.9689E 01 M$$S73298Yh 6.867E 01 5.423E43 2.626E-01 1.030E 03 4.419E-02 6.9756E-Of

%fy318$$[ 7.141 E-01 2.531E-03 2.491E-01 1.977E-04 3.406E42 7.0094E-Of 3F$b24 ; L,j]6 7.869E-01 2.172E 04 2.001E 01 7.364E-07 1.381E 02 7.0700E-Of 9.200E 01 5.712E 07 7.896E-02 7.040E 13 9.994E-04 7.f 435E-Of

$~? IG6L73 Nh34p00Mg 9 971E-01 1.025E 16 2.867E 03 4.324E 38 2.152E-07 7 f785E-01 Combined Factor (t) = Summation of [DCF Rstio(i) x lodine Dose Fraction (i)] over i for time interval (t),

where i= iodine isotope e

o e = g s' s a 2:

  • Ar
  • 4 0A k0A00333.s. 5.120E 04 2.740E 05 3.603E-04 f.934E-05 (LODB3 W 40A1778' 4.901 E+00 2.631E-01 3.400E+00 f.625E-0f 6 01779 4 0.1111 3.292E+01 1.767E+00 2.284E+0f f.226E+00

' O.1111 0.2167 " 2.086E+01 1.120E+00 f.44aE+0f 7.774E-O f

/ 0.2167 0.6 ' 1.764E+01 9.469E-01 f.225E+01 6.5765-01

,0.6,0,0005 J 1.912E+01 1.027E+00 f.329E+01 7 f 40E-of SM 1424 V 1.852E+00 9.942E 02 f.289E+00 6.920E-02

'1 418 1.139 ' 1.129E+00 6.062E 02 7.862E-01 4.22fE-02 11.139 + 1487 ' ' 5.120E+00 2.749E 01 3.5686+00 f.9 f 66-Of

' . J, ,1 A57 + 2 ' :'L 3.188E+00 1.712E 01 2.224h+00 f.194E 0f

' ,a 2*8(; 2.920E+00 2.047E+00

,4,,8 24 < n, 2.344E+00 f.657E+00

'94 98 . 2.225E+00 f.589E+00

, ' $6 +72 ' - 1.889E+00 f.356E+00 l Total l 7.4f3E+01 f.0$JE+0f l ICRP 30 EAB(t), or LPZ(t) = TACT III EAB(t), or LPZ(t), x Combined Factor (t) for time interval (t)

1 a l l SUBJECT EAB and LPZ Domes BY DWM/WJE DA'IE 3/20/96 from a MILLSTONE CHKED DATE j UNIT 3 LOCA l CALC # M3LOCA94/ 01048 - R3 Rev 1 d

SHEET 24 OF 29 f Table 17 ICRP 30 Thyndd Dose Adjustment (Containment Filtered leakage) k . DCF nutuo i l-131 f-132 l-133 l-134 l-135 1

4 0.716 MMMM l

} l b

i l 4 I 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.0000E+00 j 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.0000E+00 1

4 0.000E+00 0.000E+00 OA00E+00 0.000E+00 0.000E+00 0.0000E+00 '

l .. 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.0000E+00 l

. 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.0000E+00 i 6.733E 01 7.704E-03 2.671E41 2.725E 03 4.900E 02 6.9522E-01

] 6.773E-01 6.966E 03 2.660E41 2.063E-03 4.766E 02 6.9603E-Of I i 6.789E-01 6.685E43 2.655E-01 1.fl0E 03 4.706E-02 6.9633E-01

)

l .467 6.823E-01 6.119E43 2.643E 01 1.444E-03 4.563E-02 6.9689E 01 j

d x ->

)s 6.867E-01 7.141E-01 5.423E-03 2.531E-03 2.626E-01 2.491E 01 1.030E 03 1.976E-04

4. 319E-02 3.406E 02 6.9756E-Of 7.0004E41

{; gy . L 7.869E-01 2.175E 04 2.001E 01 7.396E 07 1.362E 02 7.070ff-01 "r 9.190E-01 5.733E 07 7.906E-02 7.066E 13 1.002E43 7.f435E01 ,

i 47 N .... 0.971 E-01 1.051 E-16 2.929E 03 4.433E 36 2.204E-07 7.1789E-01 1 Combined Factor (t) = Summatum of [DCF Ratio (i) x lodine Dose Fraction (i)] our i for time interval (t),

wherei=mdme isotope

, *. p .

4 a =

]

l <: -

1: a i

9 0.0

  • n N . .. 0.000E+00 0.000E+00 0.000E+00 0.000E+00 l
  • LO.0177f 0.000E+00 0.000E +00 0.000E+C0 0.000E+00 1 p_otr76 0.1 tit _. 0.000E+00 0.000E+00 0.000E+00 0.000E+00 l

, ro.1111 + 0.2167 s 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1 GtLt187,02 ] 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1 > OS,0.595 > 1.696E+01 1.140E+00 1.180E+0f 7.988E-0f

) ' j'$4156;1A241 1.644E+00 1.112E 01 f.144E+00 7.740E-02 i ;at

  • 1A30 _. 1.002E+00 6.762E-02 6.977E Of 4.722E-02 j

j

'd 1R: 4.545E+00 3.075E 01 3.187E+00 2.143E 0f

' ' ~ 2'- 2.829E+00 1.915E 01 f.973E+00 f.336E-Of i

d %f6 4

24 <'

f[ 3 264E+00 2.613E+00 2.2886+00 f.847E+00 I lE'%96

' '96*720

'Z 2.465E+00 2.031E+00 f.76 fE+00 f.458E+00 l

1 l Total l 1.879E+01 8.626E+00 l l ICRP 30 EAB(t), or LPZ(t) = TACT 111 EAB(t), or LPZ(t), x Combined Factor (t) for time interval (t) 4

}

j 4

I

.... . ~ ~ .... - _. - - - .- . - -- - -w. n n 8. .

.. ~ . ~ .....u ..<. --

l

! SUBJECT EAB and LPZ Doses BY DWM/WJE DATE 3/20/96 i

from a MILLSTONE CHKED DATE i UNIT 3 LOCA CALC # M3LOCA94/ 01048 - R3 Rev 1 l SHEET 25 OF 29

! Table 18 ICRP 30 Thyroid Dose Adjn=*==t (ESF I4akage) l b DCl- Ratso l I-13f I-132 1-133 l-134 l-f35 l 0.718 0.440 MM 0.562 1

1 l

eo -

e i *

$ l l k CLOf 0.q00833 a 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.0000E+00 0 it' O.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.0000E+00 l l,60011I @O([ 8.096E 01 8.439E 03 2.661E 01 3.523E-03 5.044E 02 6.9448E4f

! .';' O.S 1 e<  : 6.753E 01 7.324E 03 2.886E-01 2.378E-03 4.837E 02 6.9565E-0f

7 3.7 j 4 3 J 7~.'~'

~

f 6.834E 01 5.962E43 2.830E-01 1.369E43 4.546E 02 6.97f fE-Of 1

0"Ji8]C 7.142E41 J g;'8446 g Q 7.869E 01 2.526E 03 2.189E 04 2A01E41 2.000E-01 1.967E44 7.353E-07 3A06E 02 1.361E 02 7.0100E-Of 7.0603E-of E

' M .06 Y, 9 200E-01 5.703E47 7.896E-02 7.010E-13 9.989E 04 7.f 434E-Of l 46J730 ? 9.971E 01 1.023E-16 2.885E 03 4.304E-38 2.150E-07 7,1785E-01 l Combined Factor (t) = Summation of [DCF Ratio (i) x Iodine Dose Fraction (i)] over i for time interval (t),

l where i= iodine isotope I

i l

1 Oe9A W 333 g 0.000E+00 0.000E+00 0.000E+00 0.000E+00 l' 308thi 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.097E 01 7A23E 03 7.618E-02 8.f55E-03

""%,h 12 9 hibil{4 1.235E+00 8.359E 02 8.50 fE-01 5.8f5E-02 i ONW 2.782E 01 1.882E 02 f.930E-01 f.3f2E-02 l

x . yy 7A70E 02 5.236E42

'u::;'

di ygg tvo :4. -

6.001E 02 1.140E-01 4.242E42 8.f 43E-02

-9< T720?" 9 677E-02 6.947E-02 l Tots] l 1.129E+00 3.22fE 01 l ICRP 30 EAB(t), or LPZ(t) = TACT III EAB(t), or LPZ(t), x Combined Factor (t) for time interval (t).

I l

i i

i k

I l

4 e

i

SUBJECT Ei' A LPZ Doses BY DWM/WJE DATE 3/2096 from a MILLSTONE CHKED DATE i UNIT 3 LOCA CALC # M3LOCA94/ 01048 - R3 Rev 1

SHEET 26 OF 29 4

Table 19 EAB 0-2 Hour Dose Calculation Summary Heled%e Path

, Iltysund Whole Body (vern) (reen)

- ^ ' BynessLaekage Wrea 7.413E+01 1.212E+00 lMtWWW7111ast$ LeekampMiijbel 1.877E+01 l 9.181E+00 l l Ihne2ESFlitakage4#!*$WN] 1.129E+00 l 5.253E-03 l lbMSWWWW891 ==*> 1=Em 3 l l  !

Table 20 LPZ 0-30 Day Dose Calentattom hmmary Release Path Tinysoid Whole Body (rem) (tern) i 939% BypassImakage 7&T54? 1.063E+01 1.444E-01 IsesM Filtered Leskano*waistl 9.053E+00 l 2.182E+00 l l' lAs < J' BESFIAskaan 'M;fi#d 3.221E-01 l 6.471E-04 l l e eg s rge n e i

I p!(g~ 7 S T O T M~ r sp s

~

j 2.001E+01 2.327E400 i

.I j

7. Conclusion 4

A nummary of calculated thyroid and whole body doses from a Millstone Unit 3 Design Basis LOCA

appear in Table 19 and Table 20. These doses are within the 10CFR 100 limits of 300 rem to the thyroid and 25 rem to the whole body.

J 1

i '

i i

)

l 4

I i

^ - -~ - - ' ' * -^ " '^- - - - -

_p .= -

. . ~ . . .

g SUBJECT- '" EAB and LPZ'uoses BY DWM/WJE DATE 3/20/96

- from a MILLSTONE CHKED DATE UNIT 3 LOCA CALC # M3LOCA94/' 01048 - R3 Rev 1

SHEET 27 OF 29

. - 8. Calculation Checklist a

3

, Calculation Idantifying Number Revision i

1. . Prestration Initials l.1 1.2 Section 6.1.2 Section 6.1.3 Id//bmi

/d/E/Khl i 1.3 Section 6.1.4 4/J6/.N9fA

1.4 Section 6.4.6 h/76 /2L'ht'
2. Verification

, 2.1 Seccon 6.2.2.1 T/D l 2.2 Section 6.2.2.2 %In

2.3 Section 6.2.2.3 'NW h i 2.4 Section 6.2.2.4 h 2.5 Section 6.2.2.5 MrAn 2.6 Section 6.2.2.6 3h//h 2.7 Section 6.2.2.7  % en i 2.8 Section 6.2.2.8 Nken' j 2.9 Section 6.2.2.9 2.10 Section 6.2.2.10 N A h % -<orted w [jYgb M J W .b #

i 2.11 Section 6.2.2.11 33% h  ;

)

2.12 Section 6.2.2.15 IW4h l

3. Anoroval Initial & Date 3.1 Section 6.3.1 Pr 1 11 14 3.2 Section 6.3.2 R,. 1 O ti, 4

3.3 Section 6.3.3 k 1 t196 i 3.4 Section 6.3.4 A 1 t%9t 3.5 Section 6.3.5 IL 1 -o f f, 3.6 Section 6.3.6 Rc 1 -ts-9t,

4. Non-OA Anotications Initial & Date 4.1 Section 5.4 waived 4.2 Section 6.1.4.7 wasved 4.3 Section 6.2 waived Basis for Waiver (s)

J

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

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b SUBJECT _EAB and LPZ Doses BY DWM/WJE DATE 3/20/96 from a MILLSTONE CHKED DATE UNIT 3 LOCA CALC # M3LOCA94/ 01048 - R3 Rev 1

- SHEET 28 OF 29
9. References I
1. ~~EAB and LPZ Doses from a MILLSTONE UNIT 3 LOCA", QA Category 1 Calculation #M31DCA94/01048

-R3, Rev. O, Sept. 9,1994.

2. "2 Hour EAB and 30 day LPZ Doses from a Unit 3 LOCA", S&W Calculation 12179.12 UR(B)-227-2, Sept.

13,1982.

3. Regulatory Guide 1.4, A- .viaae Used for Evaluating the Potential Radiological Caaaam- of a 14ss of Coolant Accident for Pressurized Water Reactors, Rev. 2,1974.
4. TACT III, Atmospheric Transport Code System, Oak Ridge National laboratory, CCC-447, version 83.0.
5. Report of rammi eett 11 on Permissible Dose for laternal Radiation, ICRP Publication 2, Permagon Press, New York,1959.
6. "EAB and LPZ Doses from a Unit 3 LOCA", QA Cat. I Calculation #88-019-96RA, Rev. 2, Nov2,1993.
7. Annals of the ICRP, Limits for Intakes of Radionuclides by Workers, ICRP30 Supplement to Part 1, Volume 3, No.1-4, Permagon Press, New York, First Edition,1980.
8. NRC Standard Review Plan 6.5.2, Rev. 2" Containment Spray as a Fission Product Cleanup System", NUREG-0800, Dec 1988.
9. " Accident Source Terms for Light Water Nuclear Power Plants", NUREG-1465, February 1995.
10. Millstone Nuclear Power Station Unit 3 Final Safety Analysis Report.

I1. NRC Standard Review Plan 15.6.5, Appendix B, " Radiological Consequences of a Design Basis lass of Coolant Accident leakage from F=-iaaared Safety Feature Components Outside of C='alamaat", Rev.1, July 1981.

12. DiNunno, J.J. et. al., Calculation of Distance Factors for Power and Test Reactor Sites, TID-14844, U. S. .

Atomic Energy ramminaion. March 23,1%2. l

13. Code of Federal Ramdatiaan.10CFR Part 100 - Reactor Site Criteria.
14. NRC Branch Tachnient Position CSB 6-3, "Determinatian of Bypass leakage Paths in Dual cantainment  !

Plants", Rev. 2, July 1981.

J l

15. Mdissana Nuclear Power Station Unit 3 Technical Rpa-incations, section 3.6.1.2, Amendment 89.
16. NRC Riandard Review Plan 6.5.3, Rev. 2, " Fission Product Control Systems and Structures", NUREG-0800, l July 1981.
17. S&W Calculation 12179-RP 194-0, PSAR Source Term, July 27,1977. I
18. " Transient Sump pH and Iodine Partition Capricients folicwing a LOCA", S&W Calculation 03703.1971 i

US(B)-350 0.

SUBJECT EAB and LPZ Doses BY , i/WJE DATE 3/20/96 from a MILLSTONE CHKED _ DATE UNIT 3 LOCA CALC # M3LOCA94/- 01048 R3 Rev 1 SHEET 29 OF 29

19. " Mixing Rate Between Sprayed and Unsprayed Regions within Containment", S&W Calculation 03703.1971 l

US(B)-349.0, Sept.1,1994, i

20. " Calculation of Particulate, F*a*=1. and Plate out Iodine Renmal CoefBenents for Elevated Ca=*=3a-*

Pressure Case", S&W Calculation 17273.09 US(B)-341 1, Sept.1,1994.

21. PTSCR #3-25-95.

4 1

1 l

l I

1

SUBJECT EAB and LPZ Doses .3Y DWM/WJE DATE 2/25/96 from a MILLS 1DNE CHKED DATE UNIT 3 LOCA CALC # M3LOCA94/ 01048 . R3 Rev 1 SHEET (Appendices)

10. Appendix A: EXCEL Spreadsheet Functions and Formulas

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= 13 0 0-0 008135 0 0 0 0 0 =GB081f>SC38tf>EstVf>SE5fff>GPW8vf3

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22 cmeasus8hsene = Samouseheerf 23 te 1 26 26 TACTW CAP 30 i'

27 Thus teorwel(Hrul EA8 LP2 EA8 AM 29 0 0- O rvutett 0 0 =829'8Gf3 =C28"SGt3 29 0 nm*** - 0 08111 0 0 =829'SG14 =C29*SGf4 30 0 58111-0 S 010FF 0007423 =83fr$GfS =C3tr$G1S 31 05-t 1235 00835e =837 sGfe =C3f-8Gfe +

32 1-2 0 2782 0 01882 =832*SGf F =C32'SGf F 33 28 0 0747 =C33"SGf8 34 8 24 0 00001 -C3csGfe 36 24-98 0114 =C35*8C30 36 e8 720 00e877 =c3s SG21 37 Teod =suant0200M1 esuan\E2e E3tn 38 c w sefase.etPre=rActm 4

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SUBECT EAB and LPZ Deses BY DWM/WJE DATE 2/25/96 ~

fhxn a MILLSTONE CHKED DATE UNIT 3 LOCA CALC # M3LOCA94/ 01048 - R3 Rev 1 SHEET (Appendices)

11. Appendix B: Reviewer's Comments Reviewer's Comansent Resolution
1. (2/25/96) - When mixing volumes change, the Agreed. However, this would have maant a larger wu--=-+ , Sag activities should have changed also, amount of activity would have been in the sprayed region and a lesser annmt in the unsprayed region.

n-a-ing in this fashion would reduce the thyroid dose.

Thus, the calcis conservative as is.

2. (2/25/96)-See attached pages The errors in inputs were cor.1sted. New TACT runs were run and the old results and outputs were replaced.
3. (3/20/96 - P2EPARERS COMMENT:) In the A new earlier reference was found (S&W calc.12179-process of ==, Mag the Control Room Dose RP-1944) which listed Xe-138 correctly. This new calculation using this calentation as a reference, an reference was included in this calc. and all calculations inconsistency was noted between S&W calc. mere revised accordingly.
  1. UR(B)-227-2 and FSAR Table 15.0 7. The S&W calc. which 333 used as the source term reference had Xe-138 listed incorrectly (10 times too small).

i l

l SUBJECT EAB and LPZ Doses BY DWM/WJE DATE 2/25/96 from a MILL STONE CHKED , DATE UNIT 3 LOCA CALC # M3LOCA94/ ' 01048 - R3 SHEET 20 OF 30 l

Tait Ill Input Data Set - (Contaonenent Foltered Leakage) 2 2 19 5.930E+02 6.020E+02 2 2 20 1.980E+01 2.010E+01 2 2 21 6.980E+01 7.090E+01 3 20 1.166E+06 1.184E+06 1031 0.0 0.0 3.946E+04 1032 0.0 3.946E+04 0.0 17 6 0 4.300E-04 2.910E-05 3.470E-04 0.0 0.0 0.000E-00 1 20 B.333E-03 1.778E-02 2 22 2.260E+06 2.290E+06 2 23 3.230E+06 3.270E+06 2 24 5.060E+06 5.140E+06 2 25 5. 910E+ 06 5.990E+06 2 26 4.660E+06 4.740E+06 i 2 29 3.920E+05 3.980E+05 2 2 10 9.830E+05 9.910E+05 2 2 11 2.190E+04 2.220E+04 2 2 12 1.910E+06 1.940E+06 2 2 13 2.680E+06 2.720E+06 ,

2 2 14 3.470E+06 3.530E+06 i 2 2 15 1.990E+03 2.020E+03 . l 2 2 16 1.210E+05 1.230E+05 2 2 17 5.040E+06 5.110E+06 1 2 2 18 1.360E+06 1.390E+06 .!

2 2 19 1.330E+06 1.360E*06 2 2 20 4.540E+06 4.610E+06 2 2 21 4.470E+05 4.530E+05 i

- 1 20 1.778E-02 .-

5 20 2.510E+01 1. +00 7 20 1 260E+ 0.0

- 1 20 -0 2.167E-01 1031 0.0 0.0 1.959E+05 f 1032 1 20 0.0 1.959E+05 2.is7r. w nnnr_n 0.0 1 ' M M W D g D. M k3 0 i \ d, j # k k ' ' '," ' ,' " ( ,5 f d'

  • 3 . 8.341 s.. aj #(c

)N (Da-7 20({2._516E+06 20 ,,GE;?i- e.v 1031 0.0 0.0 1.943E+05 C3 v 1032 0.0 1.943E+05 0.0 3 , q 33) x9 k X O.kDDI] 49

  • 5 x! I - e 3,003 1 20 5.000E-01 5.0002E-1 -

S* e ki%

2 22 2.640E+07 1.460E+07 l'0 2 23 3.770E+07 2.000E+07 2 24 5.920E+07 3.260E+07 2 25 6.910E+07 3.800E+07 2 26 5.460E+07 3.000E+07 2 29 9.680E+06 5.330E+06 2 2 10 2.430E+07 1.340E+07 '

2 2 11 5.410E+05 2.980E+05 2 2 12 4.720E+07 2.600E+07 2 2 13 6.620E+07 3.640E*07  !

2 2 14 8.580E+07 4.720E+07 2 2 15 4.910E+04 2.700E+04 2 2 16 3.000E+06 1.650E+06 2 2 17 1.240E+08 6.850E+07 2 2 18 3.370E+07 1.850E+07 2 2 19 3.300E+ 07 1.810E+07 2 2 20 1.120E+08 6.170E+07 2 2 21 1.100E+07 6.010E+06 5 20 2. 510E+ 01 0.0 10 3 1 6.550E+00 0.0 1.943E+05 10 3 2 ~3.604E+00 1.943E+05 0.0 1231 9.500E+01 0.0 0.0 12 3 2 9.500E+01 0.0 0.0 1331 9.500E+01 0.0 0.0 1332 9.500E+01 0.0 0.0 14 31 9.500E+01 0.0 0.0 14 32 9.500E+01 0.0 0.0 17 60 4.300E-04 2.910E-05 3.470E-04 0.0 0.0 6.222E-01 1 20 5.0002E-1 8.595E-01 1 20 8.595E-01 1.024E+00 7 20 2.740E+00 0.0 1 20 1.024E+00 1.139E+00

, , et

-[.it %Y b.".

SUBJECT EAB and LPZ Doses BY DWM/WJE DATE 2/25/96 from a MILLSTONE CHKED DATE UNIT 3 LOCA CALC # M3LOCA94/ ' 01048 - R3 SHEET 21 OF 30 Tact llt Input Data Set - (Coiitarnment Foltered Leakage) 5 20 0.0 0.0 1 20 1.139E+00 1.667E+00 10 3 1 6.550E+00 0.0 1.037E+05 1032 3.604E+00 1.037E+05 0.0 1 20 1.667E+00 2.000E+00 10 3 1 6.550E+00 0.0 2.781E+04 1032 3.604E+00 2.781E+04 0.0 1 20 2.000E+00 8.000E+00 17 6 0 0.0 2.910E-05 3.470E-04 0.0 0.0 6.222E-01 1 20 0.000E+00 2.400E+01 17 6 0 0.0 1.990E-05 1.750E-04 0.0 0.0 6.222E-01 1 20 2.400E+01 9.600E+01 10 3 1 3.* +00 0. ..,o4L+v+ ~

__ l ' g g 1032 493E+0 .781E+04 0.0 17 6 0 0. 8.660E-06 2.320E-04 0.0 0.0 3 111E-01 1 20 9.600E+01 7.200&+02 17 6 0 0.0 2.630E-06 2.320E-04 0.0 0.0 3.111E-01 0/

t Table 15 Tact III Input' Data Set - (ESF Leakage)

Tact tilInput Data Set - (ESF Leakage)

MP3 LOCA (ESF) GAP RELLASE AT 30 SEC AND IN-VESSEL AT 30 MINUTES 1 10 2 8 02 20 96 0 0 3636. 0.0 0.05 0.0 0.0 9.100E-01 4.0005-02 5.000E-02 1 20 0.000E-0 8.333E-03 2 12 6.100E+01 2 13 2.180E+01 2 14 9.850E+01 2 15 1.360E+01 2 16 5.160E+01 3 10 1.069E+04 17 6 0 4.300E-04 2.910E-05 3.470E-04 0.0 0.0 0.0 1 20 8.333E-03 6.110E-02 2 12 4.560E+05 2 13 6.500E+05 2 14 1.020E+06 2 1 5 1.190E+06 2 16 9.400E+05 1 20 6.110E-02 5.000E-01 1021 5.886E-03 0.0 12 1 1 9.500E+01 1311 9.500E+01 '

14 11 9.500E+01 1 20 5.000E-01 5.0002E-1 2 12 4.100E+06 ' si i; 2 13 5.850E+06 2 14 9.180E+06 2 15 1.070E+07 '

2 16 8.460E+06 3 20 5.0002E-1 1.000E+00 1 20 1.000E+00 2.000E+00 3 10 9.357E+04 1 20 2.000E+00 8.000E+00 3 10 1.337E+05 17 6 0 0.0 2.910E-05 3.470E-04 0.0 0.0 0.0 1 20 8.000E+00 2.400E+01 17 6 0 0.0 1.990E-05 1.750E-04 0.0 0.0 0.0 1 20 2.400E+01 9.600E+01 f 17 6 0 0.0 8.660E-06 2.320E-04 0.0 0.0 0.0 1 20 9.600E+01 7.200E+02 17 6 0 0.0 2.C30E-06 2.320E-04 0.0 0.0 0.0 0/

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  • g_, 9 ' s SUBECT EA53 ar,. ,) Doses BY DWM/WE DATE 2/25/96 from aIVLLSTONE CHKED DATE UNIT 3 LOCA CALC # M3LOCA94/ 01048 - R3 Rev 1 SHEET (Appendices)
12. Appendix C: TACT lli Output l

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Docket No. 50-423 B15648 Attachment 3 Millktone Nuclear Power Station, Unit No. 3 l Millstone 3 LOCA: comparison of Different Source Tern Scenarios l

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April 1996

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U.S. Nuclear Regulatory Commission B15648/ Attachment 3/Page 1 Millstone Nuclear Power Station, Unit No. 3 Millstone 3 LOCAs Comparison of Different source Term scenarios The Millstone 3 NEI Source Tern Initiative analysis uses the Timing Extended (tex) Source Term presented above. In order to provide a context for evaluating the tex source term additional scenarios have been run using different assumptions. The results from those scenarios are presented here.

Three scenarios are presented in addition to the submittal analysis. They are outlined below:

Case 1 " Base" Configuration The " base" plant configuration is analyzed using the current licensing source term and a one minute drawdown time. (This case is presented to reflect some refinements in models, calculated parameters, etc., from previously submitted calculations.

Those modeling changes are incorporated in all four cases here.)

Case 2 Current Source, Proposed Draktdown This case incorporates the proposed drawdown time with the Case 1 (" Base") configuration.

Case 3 Submittal Analysis The analysis done to support the licensing amendment request (Attachment 3). This case incorporates the tex source term and the proposed drawdown time.

Case 4 tex Source, Current Drawdown This case incorporates the new source term with the Case 1 (" Base") configuration.

All tha analyses use consistent assumptions except where noted.

(The containment leak rate is taken to be the proposed 0.65%/ day.

U.S. Nuclear Regulatory Commission B15648/ Attachment 3/Page 2 The results from the analyses are presented in the table below:

CALCULATED BAB AND LP5 DOSES (Rem)

Current source Revised Source Case 1 Case 2 Case 3 Case 4

(" Base") (Submittal)

Drawdown 1 min. 30 min. 30 min. 1 min.

EAB 0-2 hr .

Thyroid 67 574 94 45 Whole Body 17 21 10 10 LPE 0-30 day Thyroid 18 45 20 18 Whole Body 2.8 2.9 2.3 2.3 Observations At an intuitive level the proposed change in drawdown times makes sense given our current mechanistic understanding of the source term. Recognizing this allows some interesting obcervations to be made.

Whole Body Doses, all cases The change in whole body cases is negligible for LPZ doses, and not vast for any EAB case. The decrease in the tex cases can be attributed to decreases integration duration.

Case 1 (Base) to Case 4 (TEY Source. Current Drawdown)

This comparison isolates the effect of the new source term coupared to the base case analysis. The table shows that applying the tex source term to the current configuration reduces the calculated thyroid dose by about one third for the EAB and the whole body EAB dose by about 40%.

l U.S. Nuclear Regulatory Commission B15648/ Attachment 3/Page 3 Case 1 (Base) to Case 2 (Current Source. Proposed Drawdown)

This comparison shows that a change that makes sense from a safety standpoint is not possible using the current source term as the basis for analysis. The EAB thyroid dose goes up by an order of magnitude.

Case 1 (Base) to case 3 (Submittal)

The submittal results in an increase in calculated EAB thyroid doses. By using a full RST source term (timing + physical and chemical form) doses would have been lower than calculated in Case 3, possibly even lower than Case 1 (Base). This is indicative of the tradeoff that takes place when using a simplified approach such as the Timing Extended source term.

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