ML20213E530

Forwards Estimates of Containment Matrix & Release Fractions for Associated Accident Sequences,In Response to 830525 Memo

ML20213E530
Person / Time
Site:	Susquehanna, Columbia, 05000000, Satsop
Issue date:	08/02/1983
From:	Sheron B Office of Nuclear Reactor Regulation
To:	Hulman L Office of Nuclear Reactor Regulation
References
CON-WNP-0622, CON-WNP-622 NUDOCS 8308150157
Download: ML20213E530 (6)

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RSB S/F: Branch Misc.

JCarter R/F BLheron JRosenthal AUG 0 21983 JCarter MEMORANDUM FOR: Lewis G. Hulman, Chief Accident Evaluation Branch, DSI FROM: Brian W. Sheron, Chief, Reactor Systems Branch, DSI

SUBJECT:

CONTAINMENT MATRIX AND RELEASE CATAGORIES FOR WASHINGTON NUCLEAR PLANT 3 This memo is in response to the memorandum from A. C. Thadani to L. G. Hulman ,

of May 25, 1983 and June 30, 1983. Attached are our best estimates of the containment matrix for Washington Nuclear Plant 3. This matrix is based on input and discussions with your staff and members of the Reliability and Risk Assessment Branch, and the work which was done on the Zion PRA.

We have also attached the release fractions for the associated accident sequences. These release fractions were taken from the material prepared for the testimony for the hearings for Indian Point Units 2 and 3.

Original siped 5 N.EM Brian W. Sheron, Chief Reactor Systems Branch, DSI

Enclosure:

As stated cc: R. Mattson R. W. Houston CONTACT: Jim Carter X29408 Xk  :

8308150157 830802 l IP ADOCK 05000347 3 _

DSI:RSB. . DS , DSf.B

'"~* J Ca r,Iek/bg ' .J.Rd6nthal. .BS o.

""7//./83 gri483 g/m3 ,

L,U!N I H 11NI'l IN I l*lH I R 1 A r.ratua u nt 1 B C F H I EFC 0.000 0.000 0.030 0.097 0.876 E 0.005 0.995 0.000 0.000 0.000 ER 0.005 0.000 0.030 .0985 0.8685 V' 1.000 0.000 0.000 0.000 0.000 RELEASE CATAGORIES 8 C F H I .

Xe-Kr 1.000 0.980 0.850 0.70 5.0(-4)

I-8r 0.700 0.098 0.078 4.0(-4) 5.0(-5)

~~

Cs-Rb 0.500 0.340 0.052 0.001 1. 0 ( -5.)

Te 0.100 0.380 0.049 0.001 1.0(-5)

Sc-Sr 0.050 0.037 0.0071 0.0001 1.0(-6)

Ru 0.020 0.029 0.0043 7.0(-5) 1.0(-6)

Lc 0.0020 0.0049 6.S(-4) 1.O(-5) 2.B(-7)

• These conditional probabilities cre directly related to the totc1 probabilities for ecch accident.

)

.___-_ . =.

i j Enclosure 2 n.;- .eteD :. ,n,1 *.S E l ,a *he COntain.Ter.t bullCing ,. allure 00es a.. relatec

,.oc.

w . . c. r. .. g. .. .i e. . : r. .e e. ...sil e , *.n'c- n e X,*. ..e.

. (* in *..6 r . -.^.c..d'.. e 4. e *a - - .. . J. a. c.

.. c . . ,.. .. n...,,,,:....,

.. i.n o ...

i

... w,a.

. . . . . c . a. ;..in. . : g $ . ,ww.. e. e. a- .s g... e . . J. .e u . .m.a .o c....,.,. ..

. . . . e. .,e radiclogical release at the time cf ec..tainment buildin; f ailure. This 3 p....e5

.. c. s .e c,,....

... . )j$ge. . s ..:..

• s .. ..6.e c.:.C ^ .#. *... e " P... 0. .*.n* f. **-.'*.a..

-a

. o 4. , n' s *

. e . c. . . ..#. n o. .t " . . " . * . c-. d #. *..I

• C. # ". : .'1c. 'l e .2 s *. #. . c- . *. i c. *. s *. .*

• o" a. e n". #. . a. n...c .m . .csc.

-d Cn

.i .g..w), c. 6 C e- l *y . .* C. a s s *. .* *. - .. ". . '. #. .*. C.

1. • # b

• in *.." . * . C *on- ~. 2 . o* ... c. . ". *.

o u l' ': C' # n = .

i n........

. . . . . e.. .. . . e

.v..:....- ..- .e .el.c-.c. .

.. . .- . e . e. . .= c- . #, c r. , c ..a. . '. *. . . . . s "i n .5 e

---..=<.....g.,..

..o . . .. . .: 1 . :. .,. .= ...... s ,. n. e . c , 27'.. le= k c c. c. '. . . .. . enc . . . . c- i . ... .c-. . . .k.io. e i . i n are used as inc.ut :: the CORRAL ccce. The CORRAL anal.vsis icilews the -

radicle;ical release frem. the *ime the :: e is unc:vered to tne centain-ment building elewcewn at buiicing f ailure. CORRAL calculates the inte- -

c. rated release fractions cf Eic.n: radienuclice c.rcups as a fun::icn cf

....... 4..g r-::n, .s.... . . . . . . .

-....... ,e w

e.

. a- ... .. e * '. e . e i. e .= .e -e fc. 2. ,i v e r. -- -.o.c- #. .m. e n . '. c- 4.1 -

e -,

ure =cde ,.cr a spec 1,.1c acticen; sequence. us.nnL ca.lculat.. ns are per-

.fer:ed for all pcssible containment failure =cdes fer ea n of the damage

_his leads to a large number c,. pcten:Tal re. ease categories.

states. i . In l

. .......,e.,..s.,..

..... .. ..c x . . .. . . .=....i.=.:c.e.

. ., . . ..c. n c-

... ,wi. 4. ..

w., .e ..e. ......:..

I nine raiease categeries nsted woul, adequately represent tne iar;e nut:er .

. e.

. .=lC..lc..:e. . .. F e. l e .s .ec. .e.

i .w. e. .. e 't e .= .c e . = .. . e c a. = . .J. o. e . e.La o .w, . j o- T= ]& i .i. .i .. :. . * ...-a. ..o3 e.....

. . .. . ... . . . .c .. e.3. v.e.... ,

situations (Ca:Ec.ci.v A) 10 the release resulting fr0 a 1% *rer Ca.v leakac.e (gc..ece.y . go. .;) eic.. .. 5e ....e.c.jjo..e .=ce. .c... . . .

- e

c. . .. C o.. .=4.....en.. ...

w,.

)Cin, s e e..:*iu.e

c. . . ..o.e.e . ic.. .o-e. .s .= ... c. . .g . s .c. . .. e. s i .c e

c.e. .c ei3o - m e. r.c. . ..c )e c. e.c. .. c. .. .... , . .f. , a s I

4.c-))y. l u. so..

= . e. e.  :

-o. T.i.?.:.

4  :

,1y.. c...s ] j e. ...e s. .

y ..w. so .

3..e . in 7 c.. w l e T . .i i. ..: .. .-

l

" #. v a. t. *** #-.

tc.--T.e T.T..T.2...* 3 . . . . "c- .c-o i. .= l l a ioe o ". . . e g - ". o i e c. . l.".e r . . . c- .i # ': 1' '. '. e .c

c. w. . .e ... z . e. 's.*.e"...in*.#.

.c .

".Y ...u l *. #. ". l .V i ;n " *.o* e *r . *.. " a - i l i *.V

. #. c *. *.o ' e d .: ... c- ", E ( *. .= *. e .

.. Q,es.: .... . (.,.

r

. . . . . 4.= .- l e. .......s T; : a j

wy

.oc ...=] . . . .

.o .-..:--.9

...oct . ......

. = - 4 1 4. ..fo e...

..e yc.. 1C.Jlc.. e. c. : 'l ,., . e ... .v.oa. ( o . e : 1' n3.. i he :.a.e.,.... n..

i

, .. . . . . . . . , . . e i .i .i . : . .: ) .

. . i . ... c o . o 4. o, Table III.B.3 is exac*1y tne data neeced to perfer :ne risk analysis (r..:nu , ..... c o ...

a c ] v e. c. ) .- e..c...- . : w..e.

s ...

.. .e. .e.e

.. 4...y.

m... e. ?...

c

. .. ..=..yc.

1 a .

e t

" 9

. e

, o.

i I n

i o

t

) a l

i n c g u i t n s C i

T

i. e f f r :C G i n / V C i t t S n 1 os cn

( o i st ea 9 i n cg ni es ue ql e e

r "e e f

n r t o u ea l i t t t A a t p as C n a u t

se g O o l l l

L g

i u

ea t c e gm s n a l r b m i r a i l n aa e l e n c a I ml c t o p o e n la" l s y

o O i r o r c l e

C t i o

f S s a n t t t o H t r r i a a n g n e e r r i n e n e l p S o e

- oo r i m o O C p n Pi o c n o C O e t C a i C s El G ni f a r a s an o r t l u e f n y m ii t e n l oo a a

• l i f ne r t o ar o i r e n C o et p t I D o I s C ra S S i o y ur r a H a y l e y a 1 P i r l i p l i l

s e V l i

p n ao n V

._ f l S O f O

. e r s i

( s s l t u s W r s l a l a  :  : e  : a

- I t i p t t t  : l t p

- S a ly l l l t o l y e f f e e e l o e l l e M M M ec M I

l i

g t t M t a a n n e e e h e n l m e e r r r et r e a m m o o o ri o m

. D n n C C C ow C n i i C i

t a a y y y ) y a n t t l l l ee l t a n n r r r t l

r n o a i

- l o a a ao a. o P C C [ L f l m 1 C 1! j ,.

i lic Containment fluililing - CilAC loput .

latile lil .II.3 Itailiological iteleases fi l - - _ _ __

I f G lli 11 .

D ,

Il C telease A Category e fil'^ ^

y y y 11 ll* V, n 6, Ilt Associaleil -

l~a ilure lloile 72.0 2ll 9.4 12 3.0 2 1 13 llelease 3 1ime (liours) 11 . 0 11 . 0 0.5 0.5 0.5 11 . 0 2.0 0.5 0.5 liclease' Duralion (hours) 0.3 0 0 137 100 100 5.0 0.5 90 llelease Energy 6

(Illll/hr x 10 ) 1 67 1 , . ,

Il 1 1 1  ;;;

1 Warning 1 s

Iime (hours) '

are invent iry) llelease I ract itm ( iractions of total c 1.0(0) 7.0(-1) 5.0(-4) 9.6(-1) 1.3(-1) 11. 5(- 1 ) 1.4(-1)

Xe-Kr 1.0(0) 1.0(0) 7.0(-2) 2. 0( .1) 4.0(-4) 5.0(-6) 7.0(-1) 9.0(-2) 1.0(-1) 1.0(-1) 0.0(-1) l-fir 6.2(-2) 9. 0( - ~l ) 1.0(-3) 1.0(-5)

, 3. 4 (- 1) 9.3(-2) fl.1( -2 )

Cs- fili 7.7(-1) 5.0(-1) .__

1.0(-5) 6.4(-2) 4.9(-2) 7.0(-3) 1.0(-3) 7.5(-1) 1.0(-1 ) 3.0(-1) 4.' 4 ( - 2 )~

fe 9.2(-3) 1.0(-3) 1.0(-4) 't . 0(- 6 )

fl.6(-2) 6.0(-2) 3.7(-2) 1.l(-2) / l(-3) lla-Sr 1.0(-6) 5.6(-3) 4.3(-3) 6.0(-4) 7.0(-5) 6.1( 2) 2.0(-2) 2.9(-2) 5.0(-3)

Itu fl. 6(- 4 ) 6.6(-4) 9.0(-5) 1.0(-5) 2. 0(- 7 )

9.0(-3) 2.0(-3) 4.9(-3) 6.6(-4)

Ia

.. . . ... .-/

associa*ed prc:atility were provided fr:m Section III.A. Using nese damage states, Indian Point Units 2 and 3 plant data, and racionuclice release data, analyses and assessments were performed to cetermine new anc wr.en these c ntainment uilcings fail, ne a cun cf radionuclice releases u en failure, and cnanges in these releases cue to the presence of miti-gation features. The analysis yieldec 9 release categories, that re:re-sent :ne full spectrum of releases at ributacle :: the various c:ntainment tuilcing failure medes. These categories in Orcer cf cecreasing cesium release frac-icn, tna; is decreasing consequence i=:act, are:

Release Catecory Failure Mode -

A large seismic event $"

(containment cellapse)

B Event V and all c (alpha) failure meces C All icng-ter: 6 (delta)

L_ overpressuri:atiens and SGTR event D All early y (gamma) hydrogen burns (no sprays) .

E All late y (gamma) hycrogen * ,

burns (no sprays)

F All early Y (ca a) h.vdrecenlt turns (wi-h sprays) 1

, G -

All E (beta) failure medes 1

(failure to isolate l containment)

'- 8 H All c (epsilon) basema:

l penetration coces I All conditiens for which containmentfailurecces{

37 - - - . . . __

G Just how the pre: abilities for the various c r.tatemen f ailures are :ar-titioned among tne nine release categ:rie,s is snewn in rigure 17

.2..:. ,cr .

Unit 2 and Figure III.B.10 for Unit 3. (These figures su-mari:e the ca a i

_