ML19209A581

Fes for Facility,Section VI, Environ Impact of Postulated Accidents

ML19209A581
Person / Time
Site:	Salem, Crane
Issue date:	12/31/1972
From:	US ATOMIC ENERGY COMMISSION (AEC)
To:
Shared Package
ML18079B045	List: ML18079B044 ML19209A579 ML19209A581
References
ENVS-721231, NUDOCS 7910050020
Download: ML19209A581 (13)

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VI.

ENVIRONMENTAL IMPACT 0? POSTCI.ATED ACCI3ENTS A.

.n s. v. A A Cv.,..= v.,. S er A high degree of protection against in the Three Mile Island Nuclear Stationthe occurrence of postulated acciden:s correct design, =anufacture

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and cperation, 1 and Unit 2, is provided throu used :o est4c31sh the necess,ary high integrity of theand the quality assurance progra= gh may occur are handled by protective syste=s to placecenside c unit.

Deviations that condition.

Nc: withstanding this, and hcid the plant in a safe accidents =ight cccur, in spite of the factthe conservative pos tulate is =ade that sericus engineered safety features are installed to =1tigate :hthey are extre=cly unlikely; and that pos:ulated events.

e censequences of these The pr:bability cf cccurrence of accidenta and the quences :o be censidered frc= an enviren= ental effects spectrum cf their conse-ly:ed using bes t esti=ates of probabilities and realistic fission produc:

standpoin: have been ana-and cranspor: ass u=p t icas.

extremely cen.-rvative assu=ptions were used for the pFo' site evaluatica in releas e laced deses resulting frc= a hypothetical release urpose of cccparing calcu-fuel aqsinst the 10 CFR Part vould be received by -he population and enviro 100 si: ins acidel'ines.of fissio The ce=puted deses that se significantly less than those that will be presen rc= actual accidents would nnent 7 valuati ns.

ced in the Staff Safety

'he consideration of a spectru= ofThe Cc:=issien issued gf f ance to Applicant accidents with assu=ptions as realistic aspte=ber 1,19 71 he sta:e of knealedge per=its.

The Applican:s'

' Environ = ental Report response is ccntained in Operating License Stage" for the Three Mile Isla d uclear Statien, Uni:

1 and Unit 2, da:2d December 10, 1971.

n The Applican:s '

2st=p; ions and :pidance issued as a p repreport has been avsluated using the standa tre ~0 by che Cc=rinston csed Annex to Appendix 0 cf 10 CFR 2

Decenbar 1,

ci.hnts and occurrences ranging in severit

'.ine classes of postulatad l??L.

are identified by the Cc= ission.

y frc= t rivial to very sericus 3tential consequence end of the spectru: h!n general, accidents in the high the icw potential cr ave a lev cccurrenca rate, =- > " es e t

unples selected by the Applicantssquence end have a higher occurrence rate.

The e ex4=;1en selec:cd are reascnably hc=cgeneous in ter=sfor :hese classes are shcun a exceptions.

ilure cf :he waste gas decay tank as an awas censidered to be =cre apprcpriate to clas s y (1) the ass 8) and (2) the s team generator tube rupture asccident in Class 3 (Applica=:s use an acciden t in Class 5

.k"A P03 OGM 8

3.i-t (Applican:S uSe class 8).

The follCwing aS$unptions made 'Oy the ApOli:an:3 are questionable:

(1) no S:ean genera:er tube leaks prior :D :he S:can gene.a.o.

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8 Table 20 indicates tha: :he realis tically estinated radic1cgical consequences of the postula:ed accidents would result in exposures of an assumed individual at the site beundar/ :o concentrations of radicactive materials wi:hin or comparable to

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The :able also sh us that the estica:ed in:egra:ed exposure of the population wi:hin 50 =iles of the plant frc= each pos:ula:ed acciden: would 'ae orders of

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. 3. g. e.1 3 '.g w u p.

. %. g. m ye.. 1 ) ke "ur

,. "w C.l ". '*.

A ". ? O 3. 0.., '.3..

b 3

w.

v L

I 4

VI-4 e.or_

na Answ

.y O; 3,JS t, 7 4.;D a. CCv-;...a

..D C,Ccr. >.;;..C:a-

-s_..

e e. _...

C L be S,. :...r.u. o.

.iun Clas s AIC Descriotien Acolicant's Ex2 cle(s) 1 1

Trivial Incidents None 2

S=211 Releases Cutside Con-Spill in Sa=ple Ecod tain=an:

3

' Radw2ste Sv. s:e= Failure Inadverten: Rele as e o f "cs t e G a.s Occaf s

.ca.r.

A w

4 Fission Freducts Oc Srizarf "ct applicab le Sycte: (LWR) 3 Fissica P cducts c Pri=ary One day Operati:n with P ri= ry 3.=:en

/

and Secondarv. Syste=s (?WR)

Leak tc Raac :: Suildin-$

.n. o.

3.1 c _,. _

4.

1s.,...

3,_,_ c,..3......

i f..

Tuba Lazi and Release frc: Ccndenser 6

Refueling Accidents Drep of Fuel Asse:bly or Drep cf Heref Cbject en Fuel Ass e bij 7

Spent Fuel Hand' ing Accident Drop cf Fuel Asse:bly

.I L*

.- ye..aa

=d-0, =..... d.. o,

?. s.

.. d. '...

i.

3

.4cn.4 2e,..

7.,. 4. 4s a ~. 4....

..e..a-u Ccnsidered in Design Basis Ch an ges Evaluation in the Safe:y Startup Acciden:

l Analysis Repor:

Ecd Wit'..raval Accidenc Cold Watar Acciden i

T o s s o.*

F.

%._1_.-~. :*..

n.

J J.eu.

e, u

S tuc' -Cut, Stuck-in, or Dr:pped CC u

.,1 o.n A

4. c e ~.. ~.

w..

w Less C.: c 1 a n... t. T.. A.

n C. t. w,.....

a

...w vs S tea = Line Failure Stes: Line Leckage Stas = Geners:c: Duba Failure Rod Ej ectica Acciden:

Ln s n.e C, o.,....

.ue.

.<a

.a a

Wcs:e Gas Tank ?.up:ure l.

9 Eypcthe:ical Sequences of Sene e..,..

..,.w-.

,4,....a.

v.kJ....

.J Class S f

n I

E00RORGMR nu m t

a

VI-5 Ta_T 7_

7.0 aU S'.',IciA?Jf 0F ?>.DICLCG*. CAL CCNSEQUENCES CF ?0STUI).TED ACCIDENTS (Single Unit Cnly)

Esti=ated Dose Esti=ated Fraction of to ?cpulation 10 CFR Far: 20 L1=1:

in 50 Mile at Site 3cendar:1/

Radius. =an-re:

Class Event 2/

2/

1.0 Trivial incidents 2/

2/

2.0 S all releases cu: side centain=en:

3.0 R2dvaste sys:e= failures 0.073 10 3.1 Equip =en: leakage c:

=alfunctica 0.29 10 3.2 Release of vas:e gas s:craga tank centents 0.003 0.47 3.3 Kelease of liquid vaste storage :ank centents N.A.

N.A.

4.0 Fission pr ducts to pri=ar/

systes (Sk'R) 3.0 Fissica pr: ducts to prinary and secondary systems 's?'.G) 2/

2/

5.1 Fual cladding defects and stea: genarator leaka

.CO 2 C.22 5.2 Cf f-dasi;n trcasien:s th::

induce fuel failure above the ' er.p e c:a i and s t a a:

ge.ea cr leak 0.0c6 13 5.3 Stea: g2nera:or :ube rupture

?CORBRMNIL 11013 268 Y

VI-0 L, L _,_0

(<..,.ia.s Estica:ed E:se Estimated Frac:ica cf to ?:pulatice 10 CFR Par: 20 Limit in 30 Plle Class Event ~

at Si:e Boundarcl/

Radius.

-ea

->=

6.0 Refueling acciden:s 6.1 Fuel bundle drop 0.015 2.1 5.2 Heavy cb;ec: d:cp cnto 0.26 36 fuel in cire 7.0 Spent fuel handling ac:iden:

7.1 Fuel cssembly drop in fuel 0.01 1.3 s:orage pool 7.2 Heavy object drop ente fuel 0.035 5.3 rack

7. 3 Fuel cask drop

.. A.

" A.

S.O Acciden: ini;ia:icn even:s considered in design b asis ev:luation in the safety analysis repor:

S.1 Less-of-coolan: acciden:s Scall 3:eak 0.15 40 Large Break 1.2

_1000 S.l(a) 3reak in instru:cn: line frc

" A.

" A.

pri=ary sys tc= that penetra:es the contain _n:

S. 2 ( a)

Red ej ection acciden: (?WF.)

0.12 100

3. 2 (b)

Rod drop accident (372) 5.A.

N.A.

S. 3 (a)

S :e-~ ne breaks (?WF ' s-outside containment)

S =all 3 :aak

< 0. 0 01

<0.1 Large 3reak

<0.001 0.13 j

VI-7 TA31E 20 (cont' d)

Es ti=ated E se Esti=ated F c:: tion of to Populatien 10 C7R Par 2C Li=1; in 50 P.ile Site Soundarv./

Radius, =2n-re:

1 at Cisss Event 3.J(b)

S te2=line breaks (3'JR)

N. A.

N A-

-1/ Represents :he calculated fractica cf a whole body dose of 500 =re= or

he eqd1valen: dese to an organ.

2/ These releases will be c:= parable :c the design cbjectives indicated in the proposed Appendix I to 10 CFR Par: 53 for rou:ine effluen:s (i.e., 5 ::e=/y r :o an individual f::= ei:he: licuid er gasects effluents).

~

4.

e e

P00R DulNil nos m

u.

.w VI-8 1,

,e.2.=.^.

'.a..

.k.. a.

. e a -. '.o n ". o u.' d.

-. e-k o-b '. ", S e p s..s. e

.h. e " ". a. '. e'.e-=...S S.

c e reaction ould s~op.

The reaction would no: be e:<pec:ed to con:inue

_o..

.S..en. a

1. . e"- s e co -ds a..d... o. - ' ' ' ", " u.' A. a..o.. a c u..

• =. S *. ' ". a '...'.a.'-.-

./ e is w' ".e

~.o

'...A u - *.d

. a o'.* o a c ~.'.v'. ~.~,

'.m.. ~.h. e '. u '_ '. e ' s..=. ~. ~ -.'3..'.

. e.' - *., a * *_ '-

entgens per hour at 3 feet.

There would be verf 11::10 dispersion cf 1

2 4 c ac.4.ta.

-, ~. e. 4. a..

u 2.

Irradiated uel from accidental releases of radica::ive Ef f ects on the environ =ent as *-= ed -

-e 4-a 'a*ed fue' h

"*a-

-'=-

--- d 3

e.4.,'S d u. *... s S h

• r - = *- e

'.~.". 1~'.... "..s.. *. <. a a : a " ' t. ~. e '.. ~- '.... ~., 4 =- - = '. a.. s =. ^ s e.. '. '. ".. =..-*.va~.'o h*_.'-

2S es and Coolan: are released.

( a) L e.' >..

~a =. o F.

e,... u'..*.. a. e d.

. c o l a.... a.S u '..'... 3 '...

'.y.oy>..

..'.- s... e i

g....,

e o. o.%..

• k.. -.J. 3 a.b. 3 g.. d. y c *.

. - V b

9a V 4e a 3

.3. S, 1 = c.: *3 Lm_.,.1

. b.. o.

C., S...

n. C S a. J h.1 e,'

..v.

.w a..J 3 z.,

t..,. a. ~..

.. a -,

4.. a. 2.

.a

o T. T.Cy S p e C. a. t.- p.gea.Ag.o_g. h..ac k..

4,9. L. J a.

~ s. g =. ea w

t C,.. a.. e.. 4. o..o e3 h S.4.p ee...

S..c'a an a-.4J,..

J. r

%. 4 -w..i,

a

.3 a

3.

k 4..

J

. h.. e. 9., S 3_ a e.

o.. w e '

e.. e p ' a....

b

... 4

a..' " d. '..., *.'.. =. ' 0 -v e o. l '.# a.

.e....'. o. ~'~.~.~. 3 l

a_m. 1. =. o' O.C0' C.

- a..

Leak ~>.

c.=

3 "A.

r

'roo. S/ hour is abou: the Scalles: arount of leakaze that can be de:ected b -

3 w,..., - 4.,. 3._ 3_ J.

o.. A. e. 2. C. o f

.1 2.

9.. 2 3

4 3

4. 3 L,., '.

oS..~.3.4 3 o:. 3 1. 3..... 3.. 3.,...

.e....

• b.. a *. "* h. e *....' #.". #. #. ".. '.

I, 3

w

..m.3 "w o C C.- "...

• b.. a. 3-o u7. '. "

U'd.

k. a. o*

~ *

..c..J4 q3

.1.,..

eJ.*y.pI.

' 9 L, ' M.

. 3. w* O 4.*.* a.

• 4 3..

. =. -. _,,. ) g e.. 7 *. a v 2 *f*

.-2.*

L.* M.

0 m.

g*.q - o o. M.

3. peg f.

-c s..r.? g g... n.

l

.v w

. e I

)., C'n o_.< - S,. s o.

.r l.

- s. _.- *. e 7v a S.b '.. ' #. ".";

~ #

e.... m..o.. ;.

1 da J

u. g s_ g

,...J

. o o. 3...

.a a:

.s

(*o )

0. 2_7 s.., - a.

'.q

.b. 2 J ~_g. -b 3 3.: e s.u. m.m..

C... ~. a C 'S'.".

is' #..". o ' ". *. A.

'. 7.

.'*.c

• • ~.*..=_~_=.'"j s'.'.". 3. - a..' _

.# #. 2. *.

a b., r.k.. g f

c... A. -k.. e C.'.' #..d '... - o#

'.'a"..#"*.'.

v.n Ca

'.s. C m o....,.4

3.. 43 w

3 w

4

• b a

' '.. *. m.- b 'A..' a'

• S "_.'y.".

i a.,...

w...

a 3 3 S 2.

N. '. d. a S n e a.. e..,. e., S C m '. o #.

'.h. e C. o '.' 7. '. a ~..#.

o C _ *.

3 t.

A e

t b,_.._.,,

.s.

c.o _

.s.. e o, s.<.

i m

i In such an accident, the amount of radioactive ca:erial released l

~~'d

.. 4 3.., s., 2 3-. 4.o. e :

h*

.,b ' a a e a s ** * * * " >-

w.

- 6

,,,4.

A.

. o

.w,..

...i2 4

=>

1..

13...'

.- -... -,. a.. o,

w c%aw-s-

4...

.b....

.u.1 p4CS c,.. 4 S v.. s.

3 3.

Jon o.. k....*

- i

..w..

.u.3...

..3.,.

• % a.

0...J a...-

e s

ar 4

.u w

3 4.,..

.4. 2 C o.1a...

D 2,S v*. a-

... L.1 A,...

A. o.

e,. m p. w-. 3. w w

-v v.

..r f,a.

• g

~.h. y S a_y g. a C 3 e.. A. a

2....S

.4. 4. k..,., n.1 A % a.

t...v,*.n.>.>,

t. e.. e.' s a t.. 3. _,jo. C.a.e.

.. v.

S....%..

.e.4

-:. a 1. a.., S e S oC

....ed,

.% a_n

~= v-, T 2 k a.

e.r.ye e.. s. A.

~0

~..<a.

~1.,

1.

2...

3 w

f

..s.

f.

i o

o.e.so.a

.w3_

m m

. 4... ;.

.a j

a,.

4

..o u,1 J b. 3:.:.e 3a.

t.

.u 1

A

.4_._.

0 1./ a. 4.

4.. e

e...w.

d e=.

.S

.4 3 n

. a. n. e... a.

.e3....

u,. A.. J..%. 2. n.10 0.: e a... c. eo n: th e o, c o-t A. c-...

.a

~..

. o e t. _

~4,

%.. 4 -g., 3 a.: e.. A..... a. 3. 4 ~. 4 1 1 1.,.. g...Jeg 3ya.,,3

... a..b.. e. c, J. 4.

4

. 0,.

l

.3

.=.s,..t...,

...'.a 3

t.

h t... A..e d S qu. a r e. e e >

_.4

%.... %e -,.....t.a*eA.

~. o

• .%.. e s.... a.....

c d e.. q.. ' _.*. 3 t *.0 n. (*ha". *o.

R. a n ~b - I C o n *'

• i ** ' * # c "* ' 6"* e ' - )

2- ^*

6' " o ' " *-

3 t

a

)

0 phJ

m...% e p m.. + f.

i.

. h.. e

e.. J...

p.. D..q..i D..

Y 3

..M

,e g h.,..

,. a v.

,f o

I O

I.

I I

I i

VI-9 3.

Solid Radicactive 'e'as tes It is highly unlikely that a ship =en: cf sclid radicactive vaste will be involved in a severe accident during the 4C-year life of the plan:.

If a ship ent of icv-level waste (in drurs) becc as involved in a severe accident, sc=e release of vaste =ight occur but the speci#1c activity of the was:c will be so icw that the expcsure of perscnnel veuld not be expec cd to be significant.

C her solid radioactive vastes vill be shipped in Type 3 p c( k a ges.

The prcbability of release frc= a Type 3 package, in even a very severe acciden:, is suf ficiently s all that, censidering the solid fora of the waste and the very re=cte probability that a shipeen: of such vaste would be involved in a very severe accident, :he likelihcod of significan: expos ure would be extre=aly s=all.

In either case, spread of the conta=inatica beycad the '---diate area is unlikely and, although local clean-u: =igh t be required, no significant expcsur2 to the general public wculd bi expe~cted to result.

4 Severity cf ?cstula:ed Transcortatien Accidents 1

The events postulated in this analysis are calikely but possible.

More severe accidents than those analy ed can be postula:ed and their conse-quences could be severe.

Quality assurance for cesign, canuf actura, and use cf the packages, centinued surveillance and :esting of packages and transport conditions, and conservative design of packages ensure tr.at :he prcbability o.c C.4 t.. s,

,..a.....-

c 4

a-3.,

..,. a.

.nas a..e..C..

4.

a u. < : 4...C.4,..*,..

c e,...

..a v.

o

..g f

cental risk is entre:aly low.

For these ressens, acre severe acciden:s have no: been included in the analv. sis.

3.

Alternatives to Nern:1 Transrertaticn Procedures A.4.,

4.

a., a c.,.

s,,,....,.3

.,. u t.<..-..: u 4.-,....,

r

,\\.<;,.o.

.a..,..-

.a s-..a in sep arate vehicles, adding shielding to the centainers, and constructing a

. g

.a

. a. c. < -.. c..,. en.u.e

.,.u.e

u....n. o n<rp.,.,.:.,..,

a

.au e..,. -,e./ e.,.,

4 c.

..v.

f and f rca the 3:ation, h ve been axi-inac by :;.c 3:af f :n a gene ric a ssis.

..-.s

. n.-. _., e

,. o o..,.

2..,3 n,.<...,r.,.,... v,.. u.,. e,.. < c..,...,. c :

,. p -.. g. <, n t. c e..

i c.c ci d a n : ccedi:icas is act c:nsidered to be suffi:iant :c.4 ustif" :he addi-4-?....... *-... g #. h. 3 g. s..--. L 4 ". e s.

p. s......,3.*w,.o.

3 r.t s..a a I.

4 4_

w

.u.

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?00R BRSW'L 1108 2~2

v!-10 n02c. nn'

?.eieren:es :=:

- w.>

te3. a

• 4 ?,

e.,.

2 Stan;3

-,ot$0:

a

'- 0 C" r dera

.o,24, 4an Council 38307~

3 1-

"3"13t,on a..,-.c ion

,,*'u e

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3-2 2 Develc0:en..:

• >7-

.' a v a --

co' Stron...- o and Cesiu

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