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Analysis of Accident Hazards of Storing Highly Radioactive Spent Fuel Rods in Spent Fuel Storage Pools at Nuclear Power Plants & at Other Offsite Storage Facilities
	ML19247B184
Person / Time
Site:	Salem, Zion
Issue date:	04/03/1979
From:	Webb R; LOWER ALLOWAYS CREEK, NJ
To:	;
Shared Package
ML18079A767	List: ML18079A766; ML19247B184;
References
	NUDOCS 7908080144
	Download: ML19247B184 (42)
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Cancer and other diseases that Would result.

These Substances are OCnSidered as nuclear WaS*e that nuSt be Safely disposed Of, except pCSSibly the by-product lutonium, WhiCh iS a nuclea" fuel

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age a extremely sericus hazard to the public health and safety, be-cause they can suffer accidents in which most of the radioactive substancso, chiefly, Strontium 00, Cesium-137, and Plutonium,could conceivably be severely heated, vaporized, and released (vented) into the atmosphere as smoke, through explosion or other means, to cause geographically widespread radioactive fallout contamina-tien, death, cancer disease, and genetic mutations in future generations.

Specifically, an accident involving one spent fuel storage pit could potentially result in ruining agriculture over a land area of the size of one half of the land east of the Mississippi River (500,000 square miles) for over a hundred years, due tc the release and fallout of Strontium 00 radioactivity a calciun-like substance that would enter the food chain thrcugh pl ar.: uptake and settle in human bone tissue to cause bone cancer.

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','icut of Cesium-137 would also severely contaminate agricul-tural land; and in addition it would create severe X-Ray-like radiation levels above contaminated ground, covering about 250,000 square miles for over a hundred years.

Finally, *he buildup of plutonium, which besides being radioactive is also an a:ccic bomb material, creates th' possibility of nuclear exrlo-sions occurring in a storage pit during an accident, whicP wculd disperse plutonium into the environnent.

?lutonium dust is an extremely toxic radicactive substance which causes lung and bone cancer and which lasts for thousands of years before decaying to harmless levels.

A release of a fraction of the plutonium frcm a

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_i be built on the site of water-ccoled reactors and their spent fuel s torage pools; so that a breeder reactor acciden: :co could effec a sc.ent fuel pool less of water accident.

Therefore2 reactor acciden:

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Unfc" unately, the Federal Govern-T.en; has not evaluated the severe reactor accident pcssibilities, m..a hny-. o..o,, s a-c 4.n.,. e c - 1e.a ~, u h o_...oc,,1 w..e.,

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heir potential consequences in its licensing hea"ings; so that the public has not been informed by their Severnment of the full serious-ness of the reactor acciden hara"ds, except by this author's analysis and " elated wcrks and these of cther critics (see Petition to Ccn-

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he pc tential radiaticn levels trcund a reactor site due Oc a pcs tu-laced reac;cr accident will be evaluated to dus tifv. the assusp;icn a

tha; plant perscnnel would have Oc evacuate the site and thus leave

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the s pen; fuel pool u.nattended. )

The spen fuel s:crage pcci 1cas-g cf-water accident ust be evaluated for its pctential ha-.ful ccn-a sequences because c s:crage poci will ccncain up to 2C times scre f

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the harmful ccns equences cf a reac:cr accident.*

.hus, :nis presen: repcr; is a supplenen; to T.y treatise The Acciden Mc. cards cf Nuclea" Pcwer Plants.

I; is no ed that the trea ise dces ce na.,7 r.,

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Also, since a loss-cf-water accident is a possibill y having a number cf possible causes, even without the prior cccurrence of a reactor accident, it needs to be evaluated for its ccnsequences, in order to wisely ass ess the overall risks.

Unfortunately, the Government and the nuclear industry have issued no adequate analysis 'of the loss-cf-water accident in spen; fuel s:c rase pools.

Cnly three reports have been issued concerning the sub ject:

(1)

The U. S. Nuclear Regulatcry Cc= mission's Draf t Generic Envircn= ental Inc_ac Statement on Handlina_ and S toraze of Sc. ent Lic_ht

'later ?cwer.eacter Fuel (NUEEG-C4C4, March 1978);

(2)

The NRC 's Reactor Safety S tudy, known as the Rasmuss en 2eporg which contains a crude analysis of the icss-of-water accident in spent fuel s torage pocla, and which is the only published analysis.

(3)

An analytical reper; by Sandia Laboratories of Albuquerque, New Mexico, titled " Spent Fuel Heat-up Following Lcas of Water Zuring S torage ", by A. S. Een f amin, et al. (: raft, Sept 1978, S AND,)

,ai_,.

As we shall see, only the Sandia report provides a useful analysis Of the Icss-cf-water accident; although it is far from adequate.

The Sandia reper cnly partially analyzes the Icss-cf-water accident c determine whether spent fuel will sericusiJ overhe a > but the reper: ices not analyze for the radicactivity release consequences.

Further cre, the analysis has several serious shcr:cctings which make the numerical results presented in the reper unreliable,

acccraing to this authcr's review.

Thir'presen repcr: presents a 500 0,9

2:

critique of the Sandia Report, which is a basis for the present analysis.

This critique is outlined below; but first let us dis pose of he~ NRC's enviran: ental impact report and the Rasmussen Report.

The NRC 's environmental impact report totally ignores the Icss-cf-water accident pcssibility in reactor-sited spent fuel s torage pools (despite the fact the National Envircnnental Policy Act requires a " detailed statement" of the ""isks to health and safety").

The report cnly mentiens that calculations we"e made of a loss-of-water accident occurring in special stcrage pool facilities located away frc= reactors in which cnly aged spen fuel was assumed to be accred.

(Recall that the decay heat rate is less in aged spent fuel.)

The NRC reper; asserts tha: the calcula:icns shcc. Sha Icss-cf-water would not result in a sericus heat up of one year old spent fuel; but the report cites no details of the calcula:icn ner any reference where the calculations can be found and ex2cined fcr their validity.

7.creover, a repcrt of the Sandia Labora cry in Albuquerque centradicts the NRC's statement.

In place of riscrcus scientific anal 7 sis, the NRC reper ofrers Only vague, quali:stive, and unsubstantiated asserticns, such as :

That the waste in spent fuel " represents little potential hazard to the health and safety cf the public" (p. 5-3);

That the " unde" water s:crage of aged spent fuels is an operaticn invciving an extremely 1cw risk of a catas-

t u e re is arcphic releas e of radicactivity"

p. h-13);

And that nc mechanis 4

ava11atle for the release of radic1ctive materials ffrcc "2:ed o

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-r a reac cr site pool cr away-fron-reacter pccl (p. 3-13).

Surely, at such assertions are nc acceptable substitutes fcr riscrcus, scien-

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2n introduces its section en accidents with the statement:

"A range of pctential accidents and natural phencmena events have been analyzed."

Clearly, this statement does not assure that all pcssible spen o.,,,

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anal sis applias to nuclear reactors as well.

See this author's Accident Ra:ards and Petiticn.)

The NRC's report of its Reactor S afety Stud 7--kncwn as the Rasmussen Report--addresses the pcssibilit-cf a less of water accident in spent fuel storage pools at reactor sites, and estimates h_'v

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o radicactivity release pctential to te small.

Firs tly, the report censiders cnly light storage of spent fuel--13C spent fue' rcd as s o._..u n.4 es.

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7curth1, the report assumes that C95 cf the strontium-90 that does 7

escape the spent fuel would subsecuently be absc" bed in the filters of the air ventilaticn system of the spent fuel s torage building; and the rest (15) finally escapes into the attcaphere.

The result of these assumptiens is that the Rasmussen Repcrt estimates that abcut 2CCO curies of 3r-90 wculd be released to the atmosphere in a less-cf-water accident (This value is nct 7 tated in the :.asmuss en R.eport but must be derived frcm the data given in that report.

See appendix 1).

This 2CCO curies release value should be ccmpared to the total of stent h.c million curies of strontium-90 that would be present in the 130 spent fuel assemblies assured in stcrage (a release fracticn cf about.C55), and ccmpared tc the potential release cf 75 millicn curies of 3r-90 frcm a spent fuel s torage pcci (Zion) that is now pcssible because of the planned buildup of spent fuel.

Recall that the WASH-740 report assumed a release of 15C,CCO curies cf s'rentium-90 from a reacter; so the Rasmussen

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a let u: new revie*.. the assumptions of the Rasmussen Report.

The 2s;umptions that a sericus radicactivity release will cccur cnly 2pcn fuel melting and that only the new spent fuel wculd reach

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the zircnonium fuel rod cladding to ignite (at 9CC C) and the fire to spread unrcughout the whole storage of spent fuel rods--not jus t confined to the new spent fuel regicn cf the storage.

(The plans new for close-packing of spent fuel red assemblies in the stcrage pool would prc cte the spreading of a tironiur. fire.)

Further cre, the heat generaticn potential cf a tironium fire would 'ce enough to cause spent fuel to melt without the decay heat.

It will be shcwn in the present analysis that a near full release of 3r-90 frca the entire lead of spent fuel (new and aged) in a storage pool is ccnceivable and certainly has not been "uled cut as a possibility.

It will be shcwn also that the spent fuel need not reach telting

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s, tc cccur, but that a 19CCcC level nay suffice.

The assumpticn cf 99G abscrption of the radicactivity released frcn the spent fuel by the ventilation filters is also a ters assumption, It is ccnceivable that the ventilaticn system will break dcwn in the event of a less cf water accident.

The high radiation levels frcm the exacsed unshielded spent fuel and the high air temperatures within the bud ' d'";

(the spent fuel building would heat up like an oven, to be shcwn) wculd presumably prevent maintanence of the ventilaticn system.

Also, if a reacter accident occurred, the severe site ccntamination wculd fcrce evacuaticn of the spent fuel storage f acility, as bef' ore noted, leaving the ventilation sys ten unattended.

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v.,,, _.4.,,,., n.4._, _

q., u,e

,,_4 _,a4 n,.

.t,_,,o_

_ u,2 _, m a w, 4, g 4.,.3

- e v a.,,,,..,o_

s nme vi.

m e

-.r. m w,f "_."c 3. i

, a

-ar a_.v."g _7 c o _d -"..s c e "m_7 d.

""y" "u"u" c_

" w. e >. "u_4. _' d '. r3,

a_ _d _ h. a."

^#

..t._d a. b..

o v cculd cause the radioactive vapcrs and s:cke cc vent directly Oc h-3

-l s i :,

i v V U' Uds t

91

-s q,s

,,,o o_ n

.o_ n,c n 'e

,d..4*vs

h e <, *, c s n h e.,,_s, w, _, s o 4.m.e--

6ho.. 4.,. 6,2.,,s.

_ w a_

0 ea c

..u u

v.

s s

.s e

"s.. a. v o ". *, d _' _'

4s. C ".

a" "ss 'v e' *., S u'v, C D. -

-wp -,.,3 3 _1 '..1.1. 4 P"s c*'

w.b.e

.'N.i..' u r A.

c.#

b

^

s s...

yv

., n. _1_4 '. 2 _1 y o s, e n,,.

i r C '. T a. ", *_ ", s " ^.'". ' t1 A_ s 'v '...a ' e c.e "h e e

3 _4 4..s.w 3 *- w e e s._ a 3.r.

r 11%elihecd is merely a guess, since the less-of-water accident was not scientifically analyzed for the course it Oculd take (Zirconiun v. e. _a s..u s a' a_ ".

C.a_ n. o ". *,

a* *v a t e "

'v b. _' "v

.2. 3. -,. 3.4 c r 3,

.e -,

c.y,...a., o_ j).

w s a

w v.

.v.

y its estinates cf the radicactivity release resulting frca a 1 css-cf-water accident were not base l on any scientific analycis but ins tead cnly on "rcugh estimates ", (in other words, guesses ):

Said w a r

.n.+.,<_ n n..

+ha_, e n c,.,, +v.

n e +e m,.4 _, a a u,..,_,,ss es v.e

.-a s.s c,. o u s,e. a z a _n n a,

ee v

m a-e_<

y e

and rencval under the specific ccnditions of the accidents considered telci, have not been performed."

'.s p p. -~, p. 95).

clearly, there-fcre, the Rasnussen.eport's evaluaticn of the spent fuel pcci accident hazards is useless.

_ u..e

...,a. _a _, ; e c.-,

~'.e Sandia Repcrt mentioned previcusiv, is an attempt ;c evaluate the less-cf-water accident scien*ific2117 by means of mathematical m.w e C 'v i. a.."

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-i

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~he

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^

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u

-, c v

s i va

..-v

-y..

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.t o =. ~v.4 e..s _,., a. _,A.ay

-_o ws a,. +s o, ' y

-,c n,.A a_ a

.r.. s. s m a..n H.a A, a,,..c e

a

.n v

w.

w

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s v

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'. p. o_

C " o_, " b. ' " " h. e spent fuel stcrage accident hazards arg not cc serious,

cwever, u

w 4 a-

_4.,,..e. 4..,, "' c ".. _' s..o *, s up "y c "". P a. b "s

"..".a.

s a ",

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~gk 1_* s h.a. d. ""

repcrt, as will te shcwn herein.

'.:creo ver the Sandia 's analysis g

.33,s i..,aeo"'"e a.nd a"s

e. a.

t ' "s un c ".

"y." e -' " *..' n ~

"v b. a. s',e.n.t a

d 4e a

a u

v-fuel heatup potential.

C2lculating the spent fuel heatup (temperature excursion) in a less-cf-water accident.is a formidable cathematical prcblen.

A nathematical theory of spent fuel heatup cust account for the natural ficw cf heated air through two thousand spent fuel assen'clies, t-w 4 r n e., o..,

C c n +v., 4 n< +n ~ a + C v u,., c.o n s.,.o 4

.Csema

(

2. o.

c..a., -, a a e.a

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2

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gu o

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m. b.. a. mec-s

". a. n. _ a

b..&' m,k. _17 n c n "m". ' c ".-.

o, d

o-w,4.ae.>n

..w.o chrcughout the load of spent fuel in a pool.

The fuel red temper-atures affect the air ficw and,vice 7ersa, the air ficw affect: the v..e c, s

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".*.*'.# ' a" a ".".." ^ u *::..

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ww1

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v..C ywb-y

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vu6

.Jvwyw rw v1. o..n o = v. o.

.3 s

- -2

, e n o n. W

-..w w

yv.

w

k o. C.,s.

o, C C,.,,,. p. 4 9.%w

e.. g, 4

w.v-s.

a., y. r.. e O.dp 1 w.. e 7 4 4.,,.g-

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3 greatly affect the spent fuel temperature heatup; so the rate of

..en.u.4.,,u4cn-yt.

4.,.3 u.h o.

h e, s. - a., 4.,

,s. 4

u.,c,a

,4

.e. n - c u.- -. 4 a_o s u.o.

s.

s-m.-

e m

.a.

w w,4, a 4.,.e. _

.4.3 m,

.r o.,,s 4... y c e.n..

.O,c "v o ".

't. a_.".' -.. c ~a'

.'. h i c ".. N. 4 1 '

'a

.A.

grestl" affect the spent fuel heatup are the details cf the s tcrage

"' c P. d e s.' s7.,

"a s. a dac'"s h. e ' "

s~ a.v-."'. v ' c."..'.n.a ' +.

k - --

s s "v -.n...'" e 7 ' a s a. '.+..',,

a b.t tc.h of which depends cn the length of time since a, spent fuel had been producing pcwer in the reacter and its pcwer histcry in the reacter (this decay time is sometimes called the decay pericd); and the tctal ancunt of spent fuel in the pcol.

S torage "ack desio-". 3 v a."y acccrding to the distance or spacing between spent fuel assemblies.

.#c "

.".c ".- o,. c..c. a c "v s 'v v'.*> e~ a.a".d - " c "e." c...o *- e ' 4." - c *. t

,"~e a^ea c d.".e--

.e a

a

-. -a s., s. v -.,

.A g. o..w p a n c 1 r a o.

0,s u, C,. ~ ( "p.4,.w a,,

,,,.9a 4

m e.. S --..

w e n. Ka,;

enA,

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. - CW * *] C CP.s '". 4 C ' ' ".s~. i "

"e u' a s A e~ a. s '~ a. "'.'. a en

" a. l s s e..k.'.4 a. a~.

e t o,,o s e.,

3.,,..3 n.,e

..4 n-a _ ns 4. u,s, aces, 4,

..v w

t cr e,u.ev

..u,.v. 4.. 4, e " h.e-a o

e m

amcunt cf spent fuel that can be stored in a pccL)

~~'he S andia

,_,,.. 4 -

...,a-

, a.".# c

...e d y

" a '.n. e a

"..".a c

v t "..' "w w's c c n o ". " " c "v

d. "o c-a

-.. - - y a

accetu.t for these varicus facters and prccesses.

The results are presented in its report, which analyzes a variety cf storage rack

'~

. a e"..a, y c o d e s

e-"..a,

h d a. c ' '] 'e. "* r ds, ' ". A " " * ' d '.".,- v a.."s " ' ' ' 's d c ".

a -

rates, and cther ccnditicns.

u..

1.. q-s e a p.

C w a-

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e 4,

4

., w a a 4 T. w.. o.

.', o 1 u.p e - p e m.

4. w

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,y,

~

wii-v w.. o.

o 4w

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c~. ^ ^ d d. a..". ~s c %'.'1 h e ' c^ ". a." a.

^ ". C "w e~.b.'v o <.' m' "s e

v P. A.

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.O J, c, _ ; a e. 7 0, q.. s, 4..r..J.n.3 a

a%

.eA w

w sv..

o

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ge noC4 3 7 1.,

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=.=.e d.J

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b. 4 o.b. _ M. o n.a.4s. -

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m4 e

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=o w

ej t.

.ay-

-g v.

sg g

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h. p d *s=

9

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e. w a 44

= -

A p c.4.. o...e.

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-n o

4-4-b. o

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- %.., 4-eo =

w y..n. s aj VA s

w.

~np O.. e.'.

.w C u,

e,, w, J s - -, 7,.,,1 - e b.p o y

.r. v.'..o..

, e.d r.C s A

aw

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n' o.

em an n.o t. e.w

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v.

w m

y.

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C.O c,,~,v' C a

,. o. a

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the thecry predicts that the circonium will begin to burn (react

g. u g u,.4.,,,i

e yo..n.e.-,* a.

...c. e ' e _n "w.

~'h. a "a c o."*. s "e u' 's s ' n' " "v

'..h. a_

.# 4.- a_

n a

u would cause the circenium cladding te melt Jthe melting temperature is 1c57o^1 "cw e're r, the Sandia's analysis tas not extended beyond

. 4.,,, C n.4,,..

_4,.

. C n,,,. a, e, u 4..o,.

o u e s e.,,. n e w h e

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a u u

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vu e

c. - v

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w v_

CA u 1,. o.

s n o_.,,.u

.e,, a 1 /, _4 nc _7 uu-14 n3-the pote.n.u,a,1.cw u.k.. o.

_ _4.,, o

4. o 0 y.w o _2 e

e e

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v s

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c _ s e.

4 n

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cther words, the Sandia report does not analyze the Icss-cf-water accidents thrcush its entire course to determine the potential harmful consecuences.

.o'aad,

'. h. a.

."a n c ". t us a_ s

'v..a_

. 4." c c r._d u..

+n._d tion.. " a.... c. e." _' "e" " a_

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u.

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4 4-u,.

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y

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v

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iculd prevenc the spent fuel assemblies from heating up to this ue e. 3 g.,,, u,m,o_ _ _ c 4 ". ""..s "mu'..c e's "n hi c".

"v d~h

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> e " a,. s.4 3." a d.' ".*s v^

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b

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.= c 4 4.P_4c a 4.= _4cns, 4= e w, -e o.

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3 osv._3 s

v a fire cccurring.and an uncontrolled spent fuel accident.

Eased

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pctential consecuences, the risk wculd surely not be acceptable.

.~crecver, ncne of the described design.cdif10ations are e

apparently being 1.plA=ented, and none nay be even practical.

Without the =cdificaticns, the Sandia thecry would predict 21r0cnium igniticn in a critical decay time of 7C0 days, which would span the entire reactor cperatingd efueling cycle (1 year) and beycnds,

..v o --

,,,,c_42,

m..e s a..

c s.e _ -, o.

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wg 4

o' "e " o c ' d u' - _.

's

v. c "- ' d C ^..".a~.4 s t.' n

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a "ee".'v

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c "v " ^ v _' d_a

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' o." c~ o.d e c " o..nd n_

c k._d..

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.+._4 ^ h. <tc ".' d ", e a

u a

cpened upcn a less-cf-water accident to allcw the heated air to

. b. a. Nai ' d d.".,r, ' ". A c o.' d n '." 'c ke 4."ov..".

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Ow (the bulk of the spent fuel in full stcrage pool) could not heat up to circonium ignition temperature due to its own decay heat and that the only way for it to seriously heat up is for a circonium fire to start and spread from newer spent fuel.

Eut if heated air 1: re-cycled through the fuel, due to imperfect ventilaticn, then it may be that the whole lead of spen; fuel could overheat rapidly and much more intensely.

The heatup pctential of spen; fuel is hardly explored at all in the Sandia repcrt for the case of imperfect ventilaticn; and those cases that are analyzed (medium density racks that promote air cooling) indicate that the he' tup in high density spent fuel would indeed be intense, even if only well aged (well decayed heat seneraticn rates ; spent fuel were stored.

'creever, the Sandia analysis assumes a relatively small storage load of spent fuel:

about 332 fuel rod ass clies as ccm-pared to 2112 in the Zicn pool.

It 4111 be shcwn that heat trans-mission frcm fuel rod to fuel red (mainly thermal radiaticn) has a major effect on the spent fuel heatup; so that the size mass of spent fuel in a pcol will affect the heatup:

a larger case would mean a higher peak temperature.

In shcrt, the S and' '

o"' lysis needs to be extended tc cover all stcrage ccnditicns and circumstances cf interes t.

The nex major shcr:cccing of the Sandia analysis ccncerns the mathematical theory that was used.

The theory is not adequately described; nor is the theory and its varicus assumptions dencnstrated

c te valid.

The checry contains a major 2ssumption tha may force the s pent fuel hea;up temperatures to be grcscly under-credicted.

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This theoretical prcblem will be treated in this report, It will be shcwn that it may not be possible to investigate the site cf the error by rigorcus calculaticns, because the rathematical be problem may boc".e intractabis..

The Sandia analysis dces include acte assumptions which may introduce scte ccnservatism in the pre-dictions--tendencies to cver-predict the heatup temperatures--but these may not be substantial, and may also be more than off-set by the above-mentioned scurce of error.

In addition, the Sandia theory suffers frca a lack of essential experinental verification.

The Sandia Report does ccmpare the theory with sete experimental results, but the experimenta bare little resemblance to the spent fuel ht_.,p accident ecnditions.

The experiments consisted of two parallel heated platec at a ccnstant, 2niferr temperature of 57 C between which ficwed air by natural convecticn; whereas the spent fuel accident will involve air ten-peratures which rise greatly as the air ficws up through a fuel O

acs embly--up to 9CC C temperatures--and, ccnsequently, large changes in the physical prcperties of the air ' density, and visccsity) 2nd in the air velocity, which affects friction.

Moreover, spent fuel haatup accidents will involve intense thermal radiaticn heat trans-r.dssion, whereas the experiment relied on by Sandia involved eccentially no thermal radiaticn heat transfer.

It is well estab-liched that theory--especially concerning the ficw of fluids involving heat transfer--requires riscrcus experimental verification using exact ex;erimental Icckups cf the systems to thich the theory will ce applied.

This lack cf experimental verificaticn is doubly E,.!['

O'3/i ses

,,n impCr ant because the Sandia theCry predicts little margin betieen C

the predicted maximum temperature and the ^CC C temperature limit fcr thCse spent fuel stora~e ccnditiCns thich the repCrt cCncludes e

Culd not result in a severe heatup in the event of a 1Cas-Cf-water accident.

Finally, the Sandia repCrt analyzes the spent fuel heanup potentials of loss -of-water accidents in independent, "away-frCm-reacter, spent fuel s torage pools, which sculd contain Cnly aged spent fuel.

he repCrt cCncludes that the spent fuel heatup right be limited in these pcCls, prCvided that the spent fuel is aged fCr at least two to four years, depending Cn storage rack design, hC' ever, this cCnclusiCn is of little practical inpCrtance, since

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ut The preceding critique of the Sandia report applies to the repert's analysis of spent fuel storage for " pressurized water re ac ters " ( FURS ).

The spent fuel stcrage pcols for this class of reacters are located in an auxiliary building attached to the reactor building.

For the class of reactors kncwn as " boiling water reactcrs" (EWES), the spent fuel stcrage pcc1 is located inside the reacter

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the 5W: spent fuel cculd be virtually prevented from se"icusly cverheating.

Ecwe.er, the Sandia report neglects to analyze the

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e the physical conditicn cf the poc1 after a severe reactor e:cplosion,

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the spent fuel to fal' into a pile with a ccnfiguration that cc'. tid v ~..va c 's.4 cr. 9

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In short, the Sandia report needs to be critically reviewed; for it dces not establish the full, true potential of spent fuel heatup during a 1 css-of-water accident.

Cn the cther hand, the epert does indicate that circonium fires are possible and thus shows the need for a full analysis cf the accident h2zards of spent fuel s torage pcols--of the course of an accident follcwing the initiaticn of a circonium fire--tc dete"nine the radicactivity release potential.

Puro_ cs e and Plan _o_f. Pres ent

.0,ec. ort The rurpcse of the remainder cf the present report ic :

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(2) to prove the above asserticna concerning theoretical short-cemings of the Sandia cralysis; and thus to shcw that the numerical heatup predictions in the Sandia repcrt are not

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su repcrt for Sandia's mathematical thecrv of sp-nt fuel heatop Rod a

to shcw that it is whcIly inadequate and that, therefcre,

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e release of strontium-90 and cesium-137 and possibly other radicactive subs tances, becaus e full-scale experiments cf loss-of-water in a large-scale storage pool filled to capacity with actual spent fuel would be needed--which is otviously impractical.

Also, there is no escape from the risk of spent fuel storage pcol accidents no matter how nuclear power is

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.o., e _.,.,. o_.m e m o...., m a.

.c c m... uhe yoc1 u,.ou o

e ve a six month cccling period, the quantity of storage at reactor pocls wculd still be great in terms of radicactivity, including s trentium-90 and cesium-137-..almos t as much s trontium-90 and cesium-137 as in the reactor core, or more so for pools which s ervice two reactcrs.

Zince the decay heat level of new spent n

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m for stcrage pcci water to boil away in a 1csc-cf-cooling mal-functicn is not significantly affected if asad spent fuel is nct allcwed to accumulate in the pocl.

If spent fuel were shipped to a chemical reprecessing pcci for separation of usable fuel and the radicactive waste, "here would be created the accident haza"da of the spent fuel storage pccis th2:

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_a full cf relatively new spent fuel, unlike reactor pools, which

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evaluate the hazards of spent fuel stcrage pools and the e,,_..a 4.,

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s-The remainder of this report consists of the follcwing chapters :

(1) A detailed descripticn of spent fuel assemblies and their stcrage poc13:

(2) An intrcductcry cathematical analysis cf spent fuel heatup assuming natural air convection only, tt dencnstrate the severe affect imperfect building ventilation has en the heatup of spent fuel, and Oc show the necessity of accounting for lateral heat transfer tc between fuel assemblies, in crder to then be able tc shcw the shcrtcoming cf the Sandia theory in this regard; (3) A more detailed critical review of the Sandia Report; (2) A chapter discussing the full course which a spent fuel 1cas-cf-water accident could take after a tiracnium fire starts; (5) A chapter demonstrating mathematically the land cont mination pctential cf a release of radicactivity; (6) A chapter en informatien ner',;

(7 T A chapter en non-reactor sited pocis; and

(?) A ccncluding chapter, f

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2 be stored in the Zion Pool.

Thus, tha : ion pool will contain 4

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for a Spent Fuel Storage Pool Acc id ent:

2000 curies.

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y 14 of this rsdioactivity escapes the building

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stro ntium Co, and, t o ntium 0 0, wi th half 1:.ves of 12. 0 days, SC.5 days, and 29 years, respectively.

The

."R"'s en~ironmental

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3r 00 The ma s s o f f.;e1 p e r as s a mbly i s.h5 'ITU (NURE3-Ch06, p.

G-5);

and oma cara contains 193 fuel asser.blies: hence 1/~, of a core equals 65 assemblies.

From thase data one can calculate

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release quar *ity o.' strontium 00.

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o r c ber u f A c cc c u rNS,

B C

THE FINEST IN DR AFTING SURVEYING A PRINTMAKING DIETZGEN GEN ER AL CONV ERSION TABLES Multiply by to obtain Multiply by to obtai.'

acres 43 560 square feet cubic inches 0.03463 pents (ha.)

acres 4047 square meters cuoic incnes 0.01732 c u a rts (ho.)

acres 1.562 x 10 i souare mues cuc.c yards 7 646 108 cubic centimeters acres 5645 38 scuare varas cweic yards 27 cubic feet acres 4840 square yards cubic yards 46 656 cubic inenes amceres 1/10 acamperes cubic yards 07646 cue c meters amperes 3 10' sta ta mpere s cucic yards 202.0 gallons atmosoneres 76 0 cms. of mercury cuoic yards 764 6 hters atmosoneres 29 92 incnes of mercury cubic yards 1616 pints (ha.)

atmosoneres 33.90 fe't of water cuoec yards 307 9 quarts (hq.)

atmosomeres 10.333 kgs. per sq. meter cubic yards per minute 0.45 cubic feet oer sec.

atmosonores 14.70 pounds :er so. ncn cucic yards per minute 3.367 gallons per second atmosomeres 1.C58 tons cer so. f aor cucac yards per m.:1ute 12.74 nters per second 8ntern thermal units 02520 hiegram-caicnes degreet (angle; 60 minutes Ontisn thermal units 777 5 foot pos,ds degrees (angie) 001745 i

ia n s 8ntism thermal units 3.327:10-*

norse. cower.nou rs de grees (angle) 3600 s..ond s Bntism thermal units

'054

oules dynes 1.020x10 8 grams 8ntisn thermal units 15 ologram meters dynes 7.233 10s poundais Bntisn thermai units 4.928a10*

kilowatt hours dynes 2.248x 10

counds 8 t.u. cer min.

12 96 foot pounds per sec.

ergs 9 486s10 "

Bntist. thermal units 8.t. u. pe r min.

022356 norse cower ergs 1

dyne centimeters 8.t.u. cer min.

0 01757

dowa tts i

ergs 7 376x10

foot-oounds 8.t.u. cer min.

17.57 aatts ergs 1.020x10i gra m-c entimeters 8 t.u. cer so. ft. per min.

0.1220 aatts per so. inen ergs 10 7 joules busreis 1.244 cucic feet ergs 2.390 10 "

ailo gra m-calones cusneis 2150 cuoic inch e s ergs 1.020x10 kilo gra m.m et e r s Dushels 0.03524 cucic meters

'e e t 30 48 centimeters

/

bushees 4

pecms feet 12 incres

\\

busheis 64 pints (dry) feet 0.3048 meters busness 32 c ua rts (cry) feet

.36 varas centimeters 0.3937 inches feet 1/3 yards centimeters 0.01 meters

'eet of aater 0.02950 atmosoneres centimeters 393.7 mos

'est of a nter 03826

'nenes of mercury cenhmeters 10 mdhmeters feet of aster 304 8 kgs per so. meter centimeter grams 98C. 7 c e n time t e r-d y n e s feet of mater 62.43 pounds per so. ft.

i centimeter. grams 10s meter-aaograms feet f mater 0.4335 ocurds cer sq. inen w@mstargrams 7 233:10 e pound-feet fuct pounds 1.286x10 s Bntism treemal units centimeters of mercury 0 01316 atmoseneres

'cotcounds 1.356 10 r ergs centimeters of mercury 0 4461 feet of water f oot-ocu nd s 5 C50uiO r norse. cower.nours centimeters of mercury 1360 kgs. per so. meter

'ect ocunds 1356

ouies centimeters of mercury 27 35 counds per sa 'oct foot.counds

3. 2 41 x 10-a kaogram.calenas centimeters of mercury 0.1934 pounds per so. ener f oot-cou nd s 0.1383 k.logram. meters centime'ers per second 1 969 feet er minute

'ac t-oc u n d s 3.766:10 7 knowatt-hou rs centimeters per second 003231 feet oe second

' cot counds per min.

I286x10' 8 t. units cer minute c ent: meters per second 0.036 kilometers cer ' sour foot counds per min.

0.01E67 fact.counds cer sec.

centimeters cer second 0.6 meters aer minute

'oct counds Der min.

3 010x 10 8 ncrse oower centimeters per seccnd 0.02237 mdes per nour

'ect ocunds per min.

3 241 10' kg. caiortes cer min.

centimeters cer second

3. 72S x 10 mues cer minute

' cot-counds cer min.

2.260410s naowatts cuc.c cent: meters 3 531x10 a cucic*eet fcct councs cer sec.

7 717410 a 8 t. units per m.aute cubic centimeters 6.1C2< 10 2 cu bic.ncres foot ccund* cer sec.

1318x10 a orse. oewer cunic cent meters 10*

cubic meters

'ect-ocunds per sec.

1 945:10 ag.cator es er min cuoic centimeters 1.308:10*

cueic vards

'ect-counds per sec.

>L56=108 k now a tts cubec centerneters 2.642x 10 a gadens gadens 8 345 pounds Of mater cucic cent. meters 10s aters gr.lons 3735 cutic cent:r eters cucic cent. meters 2.113:10 a pints (ha )

g rion s 0 1337 cueic 'eet cuoic cent: meters 1057x10 cuarts (ha.)

gaisons 231 cues re es cubic 'eet 62 43 pounds of mater grions 3.785:10s cucic maters cucie 'eet 2 S32:10 cuo c cms.

grions 4 951:108 cutic yards cucic feet 1723 cucic :ncnes gadons 3.755 hters cucic'eet 002832 cubic meters ganons 8

amts (%.)

cuorc feet 003704 cubic f ards ganons 4

Ouarts pa.)

cuoic 'est 7 481 garlons gadens per minute 2.228:10s cuoic 't.

,aer second cucic feet 28.32 aters gadens cer minute O C63'8 hters cer sec:nd cucic *eet 59 84 cints (ha.)

I gerns (troy)

I grvns (av.)

cueic feet 29 92 cuarts (ha.)

grrns (troy) 006480 grams cubic feet :er minute 472.0 cubic cms. per see.

gern s ('rcy) 304167

ennyweigats (troy) cuoic feet per minute 0.1247 gadons per sec.

I 380 7 avnes g*ams cubec 'eet per minute 04720 uters cer second I

grams 15 43 gh,n s (trey) cucic 'eet per minute 62.4

'us. or water cer m.n.

i grams los ecgrams cucic incres 16 39 cucic centimeters l

grams ICs minigrams cueic 'ncnes 5.787 10*

cucic 'eet grams 3 %527 ounces cucic ncres 1639 108 cuenc meters grams 3.03215 aunces (troy) cueic incr es 2.143 x 10 s cueic vards graras 3 27093 coundais cuoic incaes 4 329:102 gadons grams 2 2C5:10 '

counds cuoic.ncses 1.639:10 e inters ncrse-cower 42.44

82. units oer min a

..m.

- _.- %.- c

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i -

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d

g l

$d THE FINE ST IN Dil A F TING Cy SURVEY!NG & PRINTM AKING NM l

D I ETZ G E N GEN ER AL CONVERSION TABLES Multiply by to obtain Multiply oy to obtain ncrse cower 33.0C0 foot-counds per mm.

mdes cer eour 16093 nacmeters per nour norse power 550 foot counds cer sec.

m45 per acur 03684 mnots norse-cower 1.014 horse oower(metr'C) wes Oer nour 26 82 meters cer mmute horse coaer 10.70 kg-catones per mm.

mues cer acur cer see.

44 70 cms. :er sec. Der sec.

9erse power 0.7457 knowatts maes :er mour per see 1 467 ft. per sec. cer sec.

n orse-cower 745 7 aatts miies cer neur cer sec.

1.6093 kms. cer ar. cer sec.

ncrse oower (boder) 33.520 9 t.u. Der neur r, des per nour cer sec. 04470 Y cer sec. per sec.

ncese-ocwer (boiler) 9 304 k no* a tts mentrs 30 42

avs 9orse sc*er-nours 2547 Ontism thermal units montns 730 acurs morse cower nours 1.98x10 f oot.ocu nds montns 43 SW mmutes morse oower-nours 2.584s 1Ce ioHet monens 2 629:1C*

seconds

orse power.ncurs 641.7 haogram ca.ones cunces 3

crams i

ncrse cowermours 2.737:10s unegram-meters i

ounces 437 5 grams "orse cower mours 3.7457 wowa tt.nours Ounces 28 35 grams ncnes 2.540

entimeters ounces C625 counds mcnes ICs mas ounces er sauare men 00625

ounds cer sq. men menes

.C3

<a ra s pm t s (d ry) 33.60 cueic menes menes of mercury 0.03342 atmosoneres mts (ho )

28 97

veic ;ncres inenes of mercury 1.133

'eet of aster counds 7000 gra,as cunds 444 323 dr es e

inc9es of mercury 345 3 his. cer sq. meter nches of mer:ury 7C.73 pounds cer so. ft.

counds 453 6 grams ncres of mercury 0.4912 ocunds cer so. m.

councs 16 ounces incnes af aater 0.C02453 atmosoneres I

counds 32.17 coundals inenes of nater 007355 menes of mercury counds of.ater 001602

ve.c feet menes cf water 25 40 kgs. per 54. meter counds of -ater 2768 cucic menes

<nenes of water 0.5781 ounces per sq. m.

Ocunds of nater 0.1198 gauens

[.. %

menes of nater 5.204 osunds car so. ft.

cunds cf nater per mm.

2.669 10*

cueic feet eer sec.

e:{

incres of water 0.03613 ocunds per sa m.

counds cer :uoic foot 001602 grams cer cuenc em *'[

.uic gr a m s 980.665 dynes counds :er cucie foot 16 02 ags. :er :ve.c meter kJcgrams ICs grams counds ser cuoic foot 5 787 10*

pcunds ce cueic m. i kdegrams

/c 93 coundais sounds :er cuore foot 5 456:10' ccunds per md f:ot

%g*

=dCgrams 2.2046 counds Douads per square fect 0016C2

'eet f water bicgra m s 1.1C2 10s ton s (sn ort) counds cet scuare *cct 4 882 mgs. Der sa. meter i

adegram-calories 3 968 antism thermal units

=cunds =er s:uare ' cot 6 944n 10 2 counds er so.,nen k oegra m.caf ones 3C86 f oot-cou nds ocurds :e sauare.ncm OC68C4 atmoseneres kncgram caiories 1.558:10 a 9orse oc*er.nours

ounds =er sauare iren 2307 feet of aater adegram calories 4183

.oule s pcunds cer saware men 2 036 inenes of mercury

= d e g ra m-ca re ne s 425.6

<nogram meters ounds :er scuare men 7031 ags. cer sc. meter k degra m-calece s 1.162x10 s nuowatt nours counds =er scuare men 144 counds per sa foot kg-canones per mm.

51.43 foct.counds cor sec.

l avarts v2

'f ued ounces

g. caicnes per mm.

OC9351 morse-:cwer I

a ua rts (d ry) 6720

aic menes

<g. caicnes per mm.

0.C6972 kdowa tts cuarts (haud) 57 75

soic menes maometers 1Cs centimeters reds 16 5 feet u cr-eters 3281 feet scuare ceat meters 1973 102 ur: war mas bio m eters 1 03 meters scuare ceat: meters 1.076:103 scuare deet

=n em ete rs 0.6214 mues

[

sauare teatimeters 01550 sauare.ncmes u cmete s 1C93.6 yarcs sauare :entrete's 10' scuare meters

= acw a tt s 56 92 B.t. units :er mm.

l sava e centimeters 100 scuare mahmeters D

ascars 4 425x10*

foct counds cer mm sauare*eet 2.296x10 a ac es l

baan) woowa:ts 737 6 f act.counds per sec.

sauare 'eet 929 0 fcuare :e% meters r

Wowatts 1.341 aorse cower I

< uow a tt s 14 34 k g..caiories per mm.

scuare 'eet 144 scuare neaes 8"~*=

sauare 'eet 009290 sauare meters F '"*d

=dowatts 108

a tt s scuare 'eet J 587=10

sc are mues muowctt.nours 3415 Sntisn tnermal umts scuare 'eet 1296 scuare <aras fwm

=acwattmours 2.6 5 5 : 10+

foct ocunds squara feet 1/9 sauare yards suw woowatt ncurs 1.341 morse cower nours sauare menes 12 73 = 1 C*

ircuar mas we dewattmours 3 6:10

ouses scuare meaes 6 452 sauare centimeters * ~'

a dowa ttm ou rs 860 5 ucgram calones scuare menes 6 944r 10 8 sauare *eet

~ '"

uowatt.nours

3. 671 x 10s udogram-meters sacare memes IC*

b4,"

savare mas

,cgav 2 303

'cg. N or % N scuare meaes 645' scuare mohmeters am-

cg* X cr % N 0.4343

'Og,. N savare mues 640 acres ec:

meters 100 centimeters sauare mues 27 88:1C*

scuare 'eet dm n-ie t e r s 3 23C3

'eet scuare m"es 2 590 scuare woometers eters 39 37 menes scuare moes 3 613 040.45 scuare oras m eters 10

<nometers scuare moes 3 098x1C*

scuare yards 7""

m eters ICs muhmeters scuare yarcs 2.066x 10

acres meters 1.0936 yards scuare yards 9

scuare 'eet maes 1609:1C8 c entimeters scuare f arcs 03361 square meters A Ig 4

mues 5230

eet l

scuare yarcs 3 228:10' scuare mes ar was 16093 uometers i

souare yards 1.1664 scuare varas N

L wes 1760 l yards l

Smo. ; cess. C.) -17 3 1.3 tem o. (degs. Fa nr.). - l T

moes 1900 S l raras temo (degs F ) -32 5<9 temo. (cess. Cent.)

N'Y maes per aqur 44.70 e centimeters per sec.

tons (lon g) 2240 counds mues cer hour 38 i 'eet oer mmute ton s (sn ort) 2000

=cunds maes per acur I 1.467 I *eet per second farcs 9144 meters i

I

(

.c

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..,... e ;...-

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B THE FINEST IN DR AFTING SURVEYING & PRINTMAKING DI ETZG E N GEN ERAL CONVERSION TABLES Multiply by to obtain Multiply by to obtain acres 43.560 scuare feet cuore incnes 0.03463 pints (h1.)

acres 4047 square meters cue c incnes 001732 avartt (ha.)

acres 1.562x 10 8 scuare mues cuoic yards 7 646:108 cuoic centimeters acres 5645 38 square varas cuore yards 27 cuoic feet acres 4840 sauare yards i

cubic yards 46.656 cubic inenes amperes 1/10 acameeres cubic yards 0.7646 cunic meters amperes 33100 statamperes cubic yards 202.0 gadens atmosonares 76 0 cms. c' mercury cubec yards 764.6 hters atmosoneres 29 92 incnes of mercury cuo.c yards 1616 cents (ha.)

atmosonores 33.90 feet of water I

cuoic yards 307 9 a ua rts (taa.)

atmosonores 10.333 kgs. cer so. meter cue.c yarda per wnute 0 45 cubic feet per sec.

atmosoneres 14.70 pounds per sa..nen cubic yards cer minute 3 367 gadons per second a tmo sprieres 1.053 tons per sa. foct cubre yards per minute 12.74 hters per second Brit:sn thermal units 0.2520 kaogra m-eatories de grees (ang'e) 60 minutes Sntisn thermal units 777 5 f oor-oou nds d e grees (an g'e) 0 01745 radtans antisn thermal units 3.927:10*

norse oower+ours degrees (eng'ej 3600 seconds Britisn thermai units IC54 icuies dynes 1.020x 10 '

grams Br tisn thermai units 107.5 adogram meters dynes 7 233x10 8 poundals 8ntisn tre*me units 2.328 x 104 udowatt nours dynes 2.248x 10

counds 8 t.u. Der wn.

12.96 foot.ccunds per sec.

ergs 9 486x10 "

Sntisn t*iermal units 5 t.u. rer min.

OC2356 ncrse cower ergs 1

dy n e-cen t; meters a t.u. :er min.

0.01757 adow atts ergs

7. 3 7 6 = 10 i f:ot pounds 1

it.u. cer min.

17 57 aatts ergs 1020x108 gram centimeters 1

8 t.u. per sa. ft. cer min.

0.1220 aatts per sa. inen ergs 10 7 joules i

Ousreis 1 244 cuesc feet ergs 2.390u 10 "

kdcgram calories cusnels 2150 cucit inenes ergs 1.020x 10 8 kdogram-m eters bushels 0.03524 cue.c meters

'eet 30.48 c e ntim eters busnels 4

Decks

'eet 12 enenes I

\\

busreis 64 cints (dry)

'eet 0.3048 meters p-awar s (dry) feet

.36 va ra s musness 32 e

centimeters 0.3937 incnes feet 1/3 yards i

cent: meters 0 01 meters feet Of water 002950 atmosonores centrmeters 393.7 mia feet of mater 03826 incnes of mercury centimeters 10 mdhmeters

'eet of aster 304 8 kgs. per sa. meter centimeter. grams 980.7 centimeter dynes 1

'eet of water 62 43

ounds per so. f t.

4 centimeter grams 10s meterriegrams feet of aster 04335 counds per so..ncn centimeter grams 7.233x 10 8 pound feet f oot.cound s 1.286x10 8 Britisn thermal units centimeters of mercury 0 01316 atmoseneres tect.counds 1.356 x 10 r ergs centimeters of mercury 0.4461 feet of water

'oct courds 5 050x10 '

horse ooner-nours centimeters of mercury 1360 nas. per sa. meter foot counds 1.356 ioutes centimeters of mercury 27 85 pounds per sa foot l

' ot-counds 3.241:10-*

kdeg am caler'es centirreters of mercury 0.1934 pounds cer sa net foct counds 0.1383 wdogram meters cent' meters eer second 1.969 feet per minute foot-counds

3. 766x 10' k dowa tt.nours centimeters per second 003231 feet =er second foot counds per min.

1 296x 10 '

8 t. units per minute ce ntimeters cer second 0.036 kdometers =er 9eur f oot-counds :er min.

001667 fact.counds per sec.

centrmeters per second 0.6 meters per minute fact counds =er m n.

3.030x10' norse ocwer e

centimeters per second 002237 mises cer nour f:ct counds cer min.

3.2 41 x 10

k g.-catories cer min.

centimeters per second 3.729:10*

mdes :ec minute

'ect-ocunes :er min.

2 26Cul0 i n aow a tts

uoic centimeters 3.531x10 8 cucic'eet f ct-pounds :er sec.

7.717< 10 :

B t. units cer minute cueic centimeters 6.102x10 2 Oucic nc-es

' cot-pounds :er see.

1.319s10s norse. cower cucic cent! meters 10+

cucic meters

cct.counds :er sec.

1345:1C ug.caior es mer %n.

cucic centimeters 1.3C8:10

cubic yards

' cot-ccunds er sec.

1356x10a k u o

a t's cub'c centimeters 2.642 x 10 gadens gadens 3 345 pounds of ater

uoic ceatimeters 10s aters gadens 3735 cucic centimeters

ube centimeters 2113:10s mets Gia.)

paons 0.1337 cuore feet cuenc cent: meters 1 C57=10>

auarts (ha )

paons 231 cuo,c inc es P

uoic feet 62 43 pounds of water gadons 3.785x10 8 cucic meters cucic 'eet 2 332x10

ucic cms.

l gadons 4 951x10 $

cuo.c yards e

cu bic 'eet 1723 cu=ic incaes paons 3.735 hters

'L'-

cuoic *eet 0.02332 euenc meters paons 3

pints (ba.)

.ne cucic feet 003704 veic f ards paons 4

cuarts Dia.)

'o cucic 'eet

? 181 gadens gaens :er wnute 2 228 10' cu b:c f t. :er second """

cucic feet 29.32 hters i

gadons =er wnute 0.063C8 Sters =er second cueic feet 59 34

ints (bc.)

grains (troy) grains (av )

i cucic feet 29 92 avarts Oso.)

grains (troy) 006480 grams pMJ.

m cucic 'eet :er minute 472.0 cuesc ems. er sec.

I grain s (tro y) 004167 pennywerg-ts (trey) 8r cuoic feet per minute 0.1247 gadons cer sec.

I grams 980 7 synes

.. M <

cubic 'eet per wnute 04720 hters cer second grams 15 43 grains (troy)

C~ "~' l eet per wnute 62.4

bs. cf water =er min grams 10

,,ie g ra m s cucic 'ncnes p;.

cuoic 16 39 Oubic cent! meters grams ICs m,digrams

ve.c.ncnes 5.787:104

ue.c 'eet gra m s 0 03527 ounces cucicincnes 1.639u10*

ucic meters gram s.

103215 urces (trey) i cueic incnes 2.143x10 8 cucic yarcs j

grams 0 07C93 coundais cucic rcres 4.329 108 gadons g

grims 2 205x10 a counds

42.44 9.t. units aer min.

cucic.ncres 1.639:10e uters n

,orse.co er

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Rl r

i b' j b i Ui

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SURVEYING & PRINTA* AKING D I ETZ G E N G EN ER AL CONV ERSION TABLES Multiply by to obtain Multiply by to obtain norse-cower 3 3.0C0 fect counds per wn.

moes cer acur 16093 udometers per mour 9crse co*er 550 foot.counds cer sec.

mues cer acur 03684 ancts norse cower 1014 horse. cower (metnc) mes cer acur 2682 meters cer minute aorse cower 10.70 mg casones cer wn.

mes cer "our :er sec 44 70 cms cer sec. oer sec.

morse oowa -

0.7457 adowarts moes :er acar per sec. 1467

't. cer sec. cer see.

mcrse.co*er 745 7 natts moes er acar er see 1 6093 ams ser ar :er sec.

morse co+er (boder) 33.520 8 t.u. cer mour mes cer acur :er sec. 04470 Y er sec. er sec-nnrse power (toiler) 9 804 kdowatts moatas 30 42 cays norse-oower nours 2547 Bntism t"ermal units I

mentes 730 ours a

horse-comer-nours 1.98 s 1 C*

f oot.cound s montms 43 800 enutes norse cower nours 2.684 1C*

icules montas 2.623:10*

seconds morse cower nours 641.7 a dogra m-calones ounces 3

d'ams rcrse-comer nours 2.737:10 Mcgram-meters ounces 437 5 grains morse-cower-nours 07457 kdcaatt neurs ounces 2S 35 grSms

nenes 2.540 centrmeters ounces 0625 Ocunds inches 10s mas I

ounces er sausre inen 0 0625 Ocund s cer sa <nen

nches

.33 varas pints (cry) 33.50

a cec incnes

,ncnes of mercury 0 03342 a trnoson ore s I

p.nts Dio )

28 S7

ub c nches ecnes of mercury 1.133 feet of ater councs 444 323 3res ncnes of mercury 345 3 ags. cer sa meter ocunos 7000 grains i

-ncnes Of mercu y 70 73 counds cer sa. ft i

nouncs 4536 grs s r

.ncaes of mercury 04912 counds er so n l

Dounos 16

unces

~

.ncaes of aa'er 0CO2458 atmoseneres

ouncs 32.17

.:o vac a's nc~es of mater 007355 inc*es of mercury councs :t aater 001602 ne.c *ee t imemes :t aster 25 40

=gs. cer st meter cooncs :f ater 27 68

acic ncaes incaes at water 05781 aunces :er sa. in

vnes ;f =ater 01198 gaoons p

ine es of ater 5 204 pounds cer sa ft.

councs of ater :er in 2.669:10-

.e c feet :er sec.

f menes o* aater 003613 councs per sq in.

counds :er :acic foct 0016C2 grams er :uo.c :m

'a..

=acgrams 980.665 cynes ocurcs ser cuo'c f act 16 02 was :er cue.c -eter udegrams 10$

arams

ovacs cer cac f act 5 797 10-acunes =er cucre in.

4%

udegrams 70 93 coundais

ouncs :er ne c

cot 5 456:10' councs :er -d 'oct 3

kdograms 2.0046 counds

aunes cer sauare foct 001602 feet of ater adogoms 1.102x10 $

ton s i snort) i councs :er savare 'oct 4 382 ags. :er sa. meter

=degram-cator'es 3 968 Bntisn taermai snets l

Ocunes :er sauare 'cet 6 944= 10

=cunas ;er so nea Q

k logra m-calor'e s 3086 foot counds i

=cuacs er sauare mem 006304 atmoscaeres k dog r 3 m-calones 1.55= 10' acrse-cower acurs ocunes cer snare.acm 2 307

'eet :f nater kd: gram.cator es 4183

ou: es ecunes :er sm.are >nen

' 2.036 m:nes :t mercury udegram.caior es 426 6 udogra rn.me ter s

=cumos :er sauare.ncn 7031 ags. er sa meter adogram. calor es 1.162x 10 m kdo*att ncurs counds cor scuare men 144 ouncs per so. foot ag. cateries per wn 51.43

cot-counds :er sec.

l O ua rts 32 6 ueo cunces

= g -caiones cer wn.

009351 morse ocaer quarts (cry) 67 20 se>c.ncaes a g.-caior>es :er min 006972 adowatts I

avarts n'cuid) 57 75 cac.nenes

= dome t(rs 108 centimeters l

r:cs 16 5

'eet kdometers 3231

- et sauare centimeters 1.973x10s e.rntar mas

=do m erers 108 meters savare cen' meters 1.076s10' square 'eet kuometers 06214 mdes square centime'ers 0.1550 scuare ncnes aaometers 1093.6 farcs sauar e ceatime'ers 10*

sauare meters w

adowatts 56.92 3 !. units per men scuare centrmeters 100 scuare %d, meters

=aowatts 4 425x10

'oct.counds cor men scuare 'eet 2 296 108 acres koaaatts 737.6

'oct councs :er sec sauare 'eet 929 0 snare :eatemeters adonatts 1.341 morse.oewer scuare feet 144 sauare ne es

'owatts 14.34 kg caiories per min.

sauare 'est 009290 scuare meters adowatts 102 a a tts saware 'eet 3 587:10 e savar, mes u sow a tt.no u r s 3415 Bnt:sn tnermal units sc6 are 'eet

.1296 scuare,arss adowatt.nours 2.6 5 5 : 1C*

foot-oounds scuare feet 1,9 souare f arcs a dow e tt. n o u rs 1.341 morse-power mours sauare ecnes

1. 2 7 3 s 10+

rcular mos q

=,f o w a tt-h e u r s 3 6:10*

,o':se s I,

scuare 'c.es i6452 sauare centreters k n ow a tt. h ou r s 860 5 adcgram. calor es y

sauare #

es 6 944 108 scuare 'eet k nowatte c u rs 3.6 71 x 10s noogram meters scuare ncaes 10*

scuare mds

'eg V 2.303 1

.c q, V r N N scuare me es 645 2 scuare mweters

cge V or ai N O4343 l ic g,. X i

scuare mnes l 640 ace,s

- eters 100 l centimeters sauare mes 27 38:1C*

scuare 'eet i

meters 3 2308 l teet scuare moes

2.590 sauare aderwers meters 39 37

ncnes scuare moes 3 613 040 45 savar,.aras l 10

=dometers I

savare mes l 2 066x 10 -

meters 3 0991:a scuare, arcs m eters ICs memeters scuare f arcs

~

seres meters 1.0936 farcs

'cuare arcs i 9 scuare feet mi.e s 1.609:10s centimete rs sauare f arcs OS361 scuare mere,s maes 5290

'eet i

scuare yarcs 3 228:10 e savare maes mdes 16C93

<do meters scuare yarcs 1.1664 sayare,aras maes 1760 farcs l

temo Jegs. C.) -17 3 13 te o ccegs Fine )

maes 19C08

<aras I

temo Megs. F ) -32 5,9 maes :er acur 44 70 centimeters per sec.

I temo ;3,gs. Oent.)

!:ns Ocng) 2:40 councs

-nes cer mour 38

eet :er %nute I

tons (snor )

2000 councs r

moes per mour 1.467

'eet er second yards l9144 mete,s

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CONTESTIONS REGARDING THE ACCIDENT liA7ARDS OF

~'c'~c L 31'0 R n' " ~r.

r

~

SP"1'.4'~i o

AT THE SALEM NUCLEAR PCWER PLANT SALEM, NEW JERSEY R : C'i A R D :

B.

h.D, Febn.a ry 2 7.

' 'r 7 9 L. [

1"-l

.ti w

V

F-s CONTENTS 1.

INTRODUCTORY CONTESTION:

THE LOSS-OF-WATER ACCIDENT 2.

PHYSICAL CONSEQUENCE OF A LOSS-OF-WATER ACCIDEST 3.

POTENTI AL HARMFUL CONSEQUESCES OF THE R ADICACTI'/ITY RELEASE FROM A LOSS-OF-WATER ACCIDENT POSSIBLE LOSS-CrF-WATF.R ACC: DENT 5:

SPECIFIC POSSE-BILITIES 5.

CONCEIVABLE FOSSIBILITIES FOR LOSS-OF-WATER ACCIDESTS 6.

CRITICALITY ACCIDENTS 7.

REACTOR ACCIDENTS CAUSING A SPENT FUEL PC01. LOSS-CF-WATER INCIDENT

?;.

TERMANENT SPEST FUEL REPOSITORY AT SALEM

?.

TwPracWcafi fy o-f TheoreWc4 / Judrs/s. 7"cf EPrlv a'/*/

3 l(;, %

CCNCLUSICN f

/p y' g i, ) '._

Wu

/

l.

INTRCDUCTCRY CONTENTIOS:

THE LOSS-OF-WATER ACCIDENT The utility operating the Salem Nuclear Power Sta-tion at Salem, New Jersey--Public Service Electric and Gas Company--[?SE&G)--is requesting a license fccm the United States Nuclear Regulatory Ccmmission to store indefi-nicely up to 1170 highly radioactive, spent nuclear fuel red assemblies in each of two spent fuel s tc ra ge pools located at the reactor site. The Station consists of one operating nuclear pcwer reactor and one under construction.

Each spent fuel pool is housed in a separate fuel handling building which is located next to its respective reactor containment building. Originally, &t was ntended only to have in stcrage about 64 spent fuel assc-btles at any one time in each pool, as the plan was to ship spent fuel a wa ;. from the site for disposal at ;er a beief, 150 day cooling-cif period that a ll on the radioactivity and associ-ated heat in the spent fuci to uccay substantially. Now, however, PSE&G proposes to increase the s tc rage capacity of each storage pool, by replacing the original design of the storage racks with a rack design which allows the spent fuel assemblies to be packed in tne pool at a high density (compaction). Lhe proposed increase in st c u,e capacity would increcse the amount of long-1c<ed radio-activ.ty to be stored in the ;;e e l eighteen-Ectd. Apprcval to increase the storage capacity is requested by PSEiG 5UD l06

p3gf because there presently exists no nuclear.aste cisposa!

system for discosine of the scent fuel.

F g d-

'Wi th re spec t to the hazards of the proposed spent fuel storage increase, it is contended that-(a)

The proposed design cnanges to ;he spent fuel storage pcols w^uld creativ increase the nuclear accident hacards of the em Station w: th respect ca the health and safety of the public.

(b)

The proposed design changes would crearc many severe accident pcssibilities which could have the poten-tial for extremely disastrous consequence,. Such accidents would involve the icss-of-pool-water, he reaf te r dencminated the loss-of-water accident.

(c)

Bot.h the PSE&C's Safety Analysis Report and the Nuclear Regulatorv Commission's Saictv Evaluation Report for the proposed design changes fail to analyze the loss-of-water accident.

(d)

The potential consequences o f los s-o f-wa te r accidents are so serious that the ut itty 'PSEdG) anu the Nuclear Regulatory Ccamission's staff ust analyze them, and the Atcmic Safety and 'teensing Board (AS&uBi and the Commission itsel f must investicate anc cns. der them fcr both their likelihced ano pctcnt.ai harmfu. ccnse-quences, in order to ena'cle the Nuclear Regulatory Commis-sion, that ts, the Commission, :tse:f, to respons;bt, jJJ o

JLd d form an opinion as to whcther the proposed spent fuet storage would be " inimical to the health and safery of the publ.:" (referring to Secticn 103 of the Atomic Energy Acc) and to responsibly inform the public of the full risks to health and safetv.

tc)

.he like..nood at-a lo s s-o f-wa t e r a cc ident fL7 occurring is not remc c.e or e x t remel y low,' but rather, the probability of eccurrence.is indeterminable. More specifically, it cannot be preven mathematically or statis-tically that tne probabil.ity of such an accident occurrine>

L i n t ne t ime pe r t ad o ii,n e //]e.l W-.- rb,* t o r o ?ef, a decade.

-s is tess enan 10 0,.,

.y..__-

-l or significantly less thar, 10C'. There exists an indetermin-able ~

extremely large number of possibilities for poten-cut tially or c,necivably causing a i os s-o f-wate r accident in a s to rage pool.

rurthermcre, wny incidents associated with nuclear pcwer reac tors o f nea r-accident s, equipment malfunction accidents, and human error have occurred.

These facts indicate that the probability of a los s-o f- -

water accident is high, not low. Because of these facts, i

plus the fact that the probabi'.ity of a inss-of-warer accident is indetermina~le and the fact of the extreme o

N pctential for harmful consequences of such an c ccicent,make the prcposed storage facility unsafe.

(fi The Nuclear Regulatory Cc.mmissicn's current practice of evaluating the risks of the worn t er severe r

r, ini hjv

Ld nuclear accident passibilities by censider.ng only the likelihood of such accidents, and not e v.i i t u t i n t; and consic-ering the potential harmful consequences, is not consistent with the well-established methed of assessing accident risks, which s to consider both the likelihood and the consequences of accidents.

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7 PHYSICAL CONSEQUENCES OF A I.GSS-G F '.JATER ACCI DENT F.7 (a)

The radicactivity in spent fuel generates heat ehich must be dissipated in order tc crevent the spent fuel assemblies from overheating. For this reason and for radiation shielding purposes, the spent fuel assem-blies are stored under water. The pool water serves to re.ove the heat of the radioacttv.tj. The pool water in turn is cooled oy water circul. ting cooling systems to prevent the pool from overheating and boi l tng dry. In a loss-of-water accident the spent fuel assemblies

11 heat up to a high temperature, because natural air convec-tion and thermal radiation heat dis s: cat: nn processes are insufficient cc cool the spent f;el. The full potenttal fcr pent f u e '. heatup has yet to

'e

,cedicted c" a the r a..

}09 n

hydraultes analysis.

Souu (b)

Upper bound c a l c u l a t '. c a s exist which indicate

/

d'

/

rhat the potential ma, exist for the uranium cxide in the spent fuel to heat up beyond its melt.ng te perature at about 2300 C, even if all af the spent 'uel were stored for tan years.

s

/

/s (c)

Calculation, exists which tend to set a mathe-matical lo.ser bound of the spent fuel heatup potential.

and these csiculations ind i c a t e t',a t as a minimum the zirconium (218caloy) fuel rod cladding material will heat up to 900 C and catch on fire for spent fuel that has decayco (aged) for three years. These calculations were performed by Sandia Laboratory and are presented in a report titled " Spont Fuel Heatup Follcwing Less of Water During Storage" (SAND 77-1371, Sept. 1978, draft), by A.

S. Benjamin, et al.; hercaJter called the Sandia Report.

The Sandia Report does not calculate the fuel temperatuce rise beyond the point when the temperature

.s calculated to reach the circenium fire ignition temnerature, and subsequent circoni um clad _ge l t i,b. ( 18 5 7 C ).

P 4 l(

(d)

A circonium f i. re w oul d gene r i c e substantial additional heat with the retent;al f or mel t i ng away the cladding of the fut! rnd and a'so melting tae craniu exide fuel or raisin; the fuel to its melt og temperature of 2350 C (a'ocuc).

(el A zirconium fire which start-in raiatn e;y new spent fuel (say, three year storage ar less>, wnich would i n c '_ ad e IV, of the total planncJ s r n n :;e or less, could :nnceivably spread to old spent fuc1 p

teas.cn u:.f D G bld s

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the whole load cf spent fuel in the pcoi.

if)

Severe zirconium explosions are :anceivaale, f

due to zirconium-wa t e r, reac t t ons /.* e

'". a, w, 't 's 3 ; r r:..ur - a ir rc.e t:. :

(g)

Hydrogen explosicns a re cc t.cei vable due to the hydrogen released in a zirconium-water reaction anc / / C reac.ing with air.

(h)

Since zirconium fue' clad melting is possible, it is conceivable that the air flow passages inside the spent fuel rod assemblies could become plugged due to Ih -

K

? o re e nin efio,,He re ~rf e u prc dvc t a ncf cfu e i o molten zirconium running down tcward cooler porticns of the spent fuel and freezing there. Plugged air flow pas-sages would greatly worsen the spent fuel heatup. Also, explosive zirconium-water reactions and hydrogen explos-lons could conceivably damage adjacent spent fuel so as to canstrict air flows and thus worsen the spent fuel heatup in these assembltes as wel1.

O 1~

(i)

Strontium-90, Cesium-1 U and Piutonium are the dominant radioactive substances in spent fuel from a public hea l th ri s'c-standpoint. It is canceivable--meaning that it has not been ru ted out s c i ent i f. ca l' y--tha t a

near 1]G',

elease cf Strontion 00 anc Cc s iiim-13 7 radio-activit-from the spent fuel tnto the atmospnere would eccur in a spent fuel heatup excursion ;- a icss-cf-water accident, For s uch a nea r-100:', -e l e a s e ta accur, the spent fuel need not neces sarily reach

.elt ing me: pera ture, but i! l DUU I

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e--

r-j z g need only attain a level of anlv about 1900 C and maintain that temperature for a day or so.

The Stroncium-90 and Cesium-137 could then diffuse out of solid CO E"Ul 3C 2

such temperatures. This assumes taat the fuei rods have Icst their circonium cladding upon mel tda>>n o f the circon-ium but that the reds would maintain their red sha pe Se-cause the UO fuel pellets inside tae fuel rods would 2

have sintered together during reac tor opera tion to form a long UO3 red capable of maintaining its shape. If the UO7 rcds should c umble, air cooling ecu!d be further impeded and lead ta nigher CO, t e.mpe ra t u re s and conse-quently a greater thermal pctential for strantium and cesium diffusion out of the UO2. f" I"

.. ~.

( j. )

calculations exist which indicate that the Q 4p air inside spent fuel s t o ra gc butiding would heat up and pressuri_c due to the heat of the spent fuel (the building would become 12..e an oven). The air pressuri cation woulc burst open the building and thus a ll c.1 the adioactive vaper and smoke to escape inte the atmosphe If tha buildinE, vents were opened, the radicactive var,or and srcka 70uld conceivably escape through these vents. Zircon-

.um and hydrogen explosions could conceivabij rupture the 'cutiding as well, to allew c1 - escape of radicacitv.ty.

,r ik)

No expurimental data ca thecreticai analyses exist en which to establisn the potential for c ', c a s e g

.t.

i g

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F.1/

of plutonium in the spent f ei into the atmosphe re in a loss-of-water accident. Steam explosions, hydrogen explo-sions, and airconium explosicns are conceivable mechanisms which could pulverize large quantities o f spent fuel bear-ing plutonium and blow it into the outside environment, where the plutonium would then spread through the environ-

ment, (1)

Calculations exist which indicate that the peg Salem spent fuel s t o ra ge building could not be modified to eliminate the possibility of a zirconium fire occurring in a lo s s-o f-wa ter a cc ident. The Sandia heport suggests the possibility of modifyJ,g the ouilding to prov.de for an open chimney effect-a large hole in the ceiling and a large hole at the floor level of the building side wall, to allow perfect room air ventilation during a lo s s-o f-water accident to expel the heated air exiting f rom the spent fuel assemblies. The holes or openings would be normally closed by large doors, which would be opened in a les s-of-wat er emc rgen y to c rea t e the chimney effect.

Such a chimney effect by exceiling heated atr. would tend to limit the spent fuel heatup :emperatures, according to Sandia's analysis, but wou i a nc1 t eliminate the possi-bility of a circontam fire. Since such a c..imney feature would not eliminate the possibility of - mirconium fire, a chimney could conceivably not nave ar, mitigating effect E --

iiU J J v, 7

ffiYi at all, for the building openings would pcccide unlimited air (oxygen) to promote the spreading of the fire and would provide ready access of radioactive vapors and smoke to the outside atmosphere. Nor would the activation of the chimney (automatic or manual opening of its doors) be reliable in the case of a severe reactor accident which causes a spent fuel loss-of-water. A severe reactor acci-dent can potentially cause such a high level of radiation in and around the site that the whole site operating crew could flee in panic, leaving the spent fuel pool and relat-ed safety and cooling systems unattended. Under such a panic situation, it would not be expected thar the chimner doors, if incorporated into the building, would be opened.

(m)

A reduction in the number of spent fuel assem

/II/

blies stored in the pool could not eliminate the possi-bility of a zirconium fire occurring in a loss-of-water accident, nor preclude the possibility of a loss-of-water accident.

(n)

Emergency efforts to cool the spent fuel follow-ing a loss o f pool water could conceivabl y v.orsen the accident or otherwise have no mitigating effect. Spraying the overheated spent fuel with water /which would have to bc dor.e remotely, due to the heav', radiation emanating from the spent fuel) would cause zirconium-water reactica that cculd promote the ignition or spreading cf a zir:cnium i0 c,o IL -

j ij u f

r1 /sG fire, or cause explosions. Moreover, the heatup o f the spent fuel could conceivabl. cause the boral neutron absorb-ing material to meltdown, leaving a region n' spent fuel without enough neutron absorption to prevent a criticality should the pool be refloeded. Fur the rmo re, mhe heat of the spent fuel in a loss-of-water accident fand possible explosions) could conceivably damage the spent fuel to such a degree that the pool would continuously leak heavi-ly, should the pool be reflooded, which would result in a heavy seepage of radioactivity into the ground and nearby waters.

(o; in order to evaluate the potential for radic-Fr.1 activity release in a spent fuel pool les s-o f-wa te r acci-dent, a thermal analysis must be perfcrmed, of course.

c; : c a,;' :.

v.

The only mathematical '_heory,which c::i s t s in a form for ce :.i s t.',is

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ready use is the SFUEL computer code of the Sandia Labora-si tory, which is described in the above-men' toned Sandia Report. The Sandia Report analyzes the loss-of-water acci-dent for a spent fuel storage pool which is close to the Salem design. However, the SandL. Report

.s not sufficient for evaluating the spent fuel Scatup potentta? for Salem (nor any other spent fuel storage pool:. and, furthermore, the SFUEL ccnputer ccde is not sufficiently develoced and verified to prcvide reliable heatup temperature predic-tion w;th reascnable accuraev. To elaborate:

I" E.;n JUU

/7104 (1)

The Sandia Report does not investigate the spent fuel temperature excursion beyond the ignition of the zirconium or zirconium melting.

(2)

The Sandia Report does not analyze the to S 9 high-dens t ty s torage rack design for the +&ee ss of imperfect building ventilation, which is the case for all pressurized water reactor (PWR) storage pools, including Salem.

(3)

Sandia's mathematical theory (SEUEL)

I.2 C contains serious theoretical deficiencies which, based on independent scoping calcula-tions, may be causing the code to be drastically underpredicting spent fuel heatup tempera-tures. Foremost are the assumptions in the SFUEL theory that the temperatures of the fuel rods in a given spent fuel rod assembly and at a given clavation are t.

same (uniform temperature distribution horincntally), and that the temperature distribution inside a fuel rod at any give<. elevation i s a l s o un i. -

form.

(4)

Sandia's mathematical theor. is nct ade-Repor /and N

quately described in the Sandia

-P s

requires a systematic checking to /erify the E.. t. f '

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jyv c od e t h _.,... ;.j a nd calculationally.

(5)

A reliable mathematical theorv of spent fuel heatup may not be practical, due to ccmcu-ter l!. citations.

(6)

Sa nd ia 's S FUEI. theory has not been experi-mentally verified, contrary to the claim made in the Sand ia Report that adequate experimen-tal data exists to validate the SFUEL theory.

There experiment relied on in the Sandia Report consisted of two heated plates held at a Icw, constant and uniform temperature cooled by natural air convection; whereas the situation in a spent fuel heatup accident ts one of a highly variable temperature distribut'cn and extreme air temperatures in a red bundle configuaration. :torecver, t h e rma l radiatica heat trans f er a ided by therma l heat conduction, appear to be a crucial heat transfer proc'sses in a spent el heatup, which were tot, t

absent in the two-heated-piat experiment cited in the Sandia Report. To adequately account for thermal radiation interchange among, anc heat dissipation from, spent fuel rods in a s crage pool under a loss-of-water accident, it would be necessarv to conduct c

'T JbV

i/

i

M,. J c an experiment which includes a large scale loading of simulated spent fuel (electrically heated) or actual spent fuel. Because the electrical resistance of electrical heater firaments ts dependent on temperature, an adequate simulati6n of spent fuel heatup m.ay not be possible with electrically heated rods',

in which case it may not be possible to experi-mentally verify a mathematical theory of spent fuel heatup, because it would not be practical or safe to conduct such tests with spent nuclear fuel rods.

be criti P"1 (7)

In shcrt, the Sandia Report must cally evaluated.

(p)

It would not be pract Leal or saf e to experimen-tally investigate the radioactivity release potential of a loss-of-water accident; particularly in the event of a circonium fire, circonium melting, explosion, or other severe prccess which causes significant changes in the fuel's physical condition, because the fuel tempera-ture excursion and the interrelated racicactivity release would both depend on the physical condition o f the fuel and en the size of the spent fuel mass undergoing c icss-of-water accident. Moreover, the behavior of the spent fuel may be a func tica c f the prior aging of spent fuel 3, r.

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3

r$

in water and the physical history of the spent fuel when it was in the reactor, such as whether the fuel had under-gone overheating in the reactor in an accident.

(q)

It is not possible to accurately predict the course of a loss-of-water accidant once the zirconium cladding 'cecomes ignited. Instead, only mathematical upcer bound estimates of the radicactivity relcase potential could be developed, which presently do not exist. A near--

100i'. release of radioactive strontium and cesium is olausi-i ble

'W(O' N

?

s (r)

The Salem Safety Analysis for the proposed

/f1 F spent fuel storage supplies inadequate information on which to perform heatup calculations', for example, the pool and building dimensions are not given.

3.

POTENTIAL HARMFUL CONSECUENCES OF THE RADIOACTIVITY RELEASE FROM A LOSS-OF-WATER ACCIDENT (a)

Each spent fuel storage pool at Salem would contain at capacity f orty-five mill ion curies o f Strontium--

90 radioactivity and about the same amount of curies of Cesium-137. For comparison the L'ni ted States Atcmic Energy Ccmmission's report Theoretical Possibilities and Ccnse -

1 cuences di Major Accidents In Larae' Nuclear Pcwer Plants (WASH-740, March, 1957) ca.:. at s that the release of 0.15 millicn curies of Strontium-90 (150,000 curies) coulu cause agricultural restrictions :ver a land area equal r

'G JUU iI I

The sice of the power reac:or assumed n the.sA5h-740 Report s not "larce" ccmpared tc cresent s;ze otants.

' ASH 1740 assumes a 500 megawatt :!.e rma l Scecif;callv,

.4 Wt.) reactor wnereas each Salem reacter has a rated pwer outputof abcut 3300 M Wt.

i

~

to 150,000 square miles, which is the size of New Jersey, New York, Connecticut. Massachusetts, Rhcde Island, Ver-mont, New Hampshire, Maine, and half of Pennsylvania, combined. A los s-o f-water accident in one Salem spent fuel storage pool could conceivably release nearly all h'

of the forty-five million curies o f St ron:ium-90, o r three y/

hundred times the WASH-740 assumed release quantity of Strontium-90.

O G---->s u i n g t ha t ns m

land whien ts cantaminated more taan titty c;y s

F1 times the WASH-740 contamination Itmit for Stroncium-90 would be ruined agriculturally,

hich is a prudent assump-tion and one which is consistent with the vie.e taken in the WASH-740 Report (the WASH-740 Report asserts that Strontium-90 land contamination at tcn times the Report's contamination limit would require prohibiting dairying l&

for a very long time)2 4+ can be calculated that a spent a

fuel pool loss-of-water accident which rel eases forty-five million curtes of Strontium-90 (which cannot now be shawn to be impossible) could result in ruining agr iculturally a land area of the size of about ct.e-third of the land East of the Mississiopi River, or certainly the entire eastern seaborad of the United States and Canaca, for a hundred years or more.

r i

h'V I L. U

/

V-(b)

The release of Cesium-137 radioact ivity f rom the storage pocl into the atmosphere could result in high

\\

levels of gamma radiation ( int ense x[ra y-like radia tion )

emanating from the ground over an area equal to 150,000 square miles. The gamma radiation exposure to persons standing on the ground could potentially occur at a rate which exceeds by a factor of thirty-eight or more the healrh limit recommended by the United States Environmental Protection Agency of 25 millirems per year for total radia-tion exposure f rom emission o f radioactivi ty due to nuclear power.

(c)

No reliable estimatas exist of the potential f~2 f cancer and genetic harm that could result frcm a near full release of Strontium-90 and Cesium-137 (and other volatile radioactive materials. in a spent fuel loss-of-water accident. Such estimates are necessary and sh uld be developed, in order that the spent fuel accident hazards can be fully evaluated.

(d)

The contamination levels indicatea in (a) and (b) above apply to the boundarv of the fallout land area cones that are quantified in those sections. In the o,. r c l o s.> e 9.

.a e e.

7

) s, interior of the cones, the contamination levels would f

be much worse.

(e)

One spent fuel pool at Salem would centain the equivalent of thirty-nine tons of Plutonium-239 alpha-c.i.

3*

d b

b

/b

F19 radioactivity. If dispersed uniformly, this amount of plutonium would have the potential for causing abandonment of about five million square miles o f land, which is 1.5 times the total United States land area, including Alaska.

Se analysis exists which proves that an area of the size of Ncw Jersey, say, would not require permanent abandonment due tc a plutonium release in the event of a loss-of-water accident in one spent fuel storage pool.

(f)

It is possible that a reactor accident at E.I R the Salem Station could induce loss-of-water accidents in both spent fuel storage pools, which would then double the above estimates of potent al harmful ccnsequences.

(g)

'ven if the spant fuel pool held a minimum of spent f ue l --s ix t y-f ive fuel assemblics, oc one-third of a core, as was the original intent--the potential conse-quences o f a loss-of-water accident would still be extreme for example, a land area of the size of Ohio, or five times the s in ' of New Jersey. could be ruined agriculturally for a hundred years or mo re, due to S trontium-90 release alone.

L.

POSSIBLE LOSS -OF-WATER ACCIDENTS :

5PECIFIC ?OS-SIBILITIES A loss-of-water accident ts pcssible, which can happen if the pool water cooling system should break dcwn.

A boil-off of the pool vater ts possible in such an event, b

J's.,v

Of which would take about four days to two weeks, based on the figure for the " maximum eva po ra t ion ra t e" (56 gallons per minute) given in the Nuclear Regulatory Commission's Safety Evaluation Report (p. 2-5). The most likely cause of a breakdown in the pool water cooling system is a severe reactor accident (see contention No. 7 below). A severe reactor accident could result in such heavy radiation levels at the reactor site that the storage pools would O.

beabfndoned. In that event the cooling system would have to be asoumed to sreakdown; and there would be no adequate assurance that makeup water could be supplied to the pool.

Such a reactor accident must be assumec to be nighly likely to occur (see contention No. 7).

There are other possibilities for d(c sing a loss-of--

pool-water accidert through a breakdown in the pool water cooling system which must be given serious consideration.

One such possibility is for the reactor plant to have to be permanently closed down due to a reactor accident, leaving caly a very small crew to perpetually watch over the storage poci and maintain ocrretual cociing. In this situation, a cooling breakdown ceuid occur througn negl.-

gence and not be corrected. Sabotage and acts o f war are cther possibtlities.

5.

CONCEIVA3LE POSSIBILITIES FCR LOSS-OF-aATER NCCIDENTS There are a number of ;cnceivab12 cosstbi.ities f"15 C

)'

JUV I L s,

O of accidents and sabotage which could result in a loss-of-

/-

water accident and which,therefore, must be evaluated for their likelihood and their potential for causing a loss-of-pool-water. They are.

(a)

Spent Fuel Shipping Cask Drop.

It appears to be possible for the heavy shipping cask to fall from i t s c ra ne into the storage pool. Such an incident should be evaluated for the potential for ruptur-ing the pool anc causing rapid drainage of the pool. A c ra ne f ailure has aircady occurred over a spent fuel stor-(%;?pi.'f: !?))

7 age poolA and an incident of improper handling of a spent V

fuel pool cask has already occurred.(6/! Ev e /~ fo ' TO.

(b)

Criticality.

Indications are that it is possible for a local criticality to occur in the storage pool (see contention No. 6 below).

Such a criticality has yet to be evaluated for the course it could take; so no upper bound exists of its thermal and mechanical consequences. It ma.

he possible that the fission heat generated by such a criticality could cause a rapid outl-off of the pool water, despite the peel water coo'ing svstem.

ic)

Sabctage and Terrorism.

F15 The possibilities for sabotage and acts of terrorism are very real. The use of explosives could destroy the cooling system, and the removal of a new spent fuel assembl:. out i ? l, r

o DUJ

of the pool water would produce such high levels of radia-tien in the pool building that action to supply a

<c water vould be severely impeded. Also, explos. es conceiv-ably could be used to rupture the pool and thereby cause rapid drainage.

(d)

Others.

Under this heading, earthquakes breaking open the pool and large airplane crashes should be considered.

6.

CRITICALITY ACCIDENTS A criticality accident in the spent fuct pool is very real possibility. Possible causes are as follows:

a (a)

Missing boral plates in a local region of a storage rack, or bcral plates with a deficient amount of Baron-10; and (b)

Underprediction of che effective neutron mullip-tication f ?. c t o r is

1 Public Service Electric anc Cas ct Company's Safety Analysis Report and the Nuclear Regulatory vommission's Safety Evaluation Report do not provide ade-cuate information to assess the hazard of a criticality accident, For example, there is

,e indication that there would net occur any resitive eacti..ty feedback effect i

during the ftssion power rise in a criticality sicuation.

It ts a valid concern that a criticality might lead to a rapid boi'-cff of the pool water-The radiation from such a high-pcwer critica'ity could conceivably obstruct J..

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, L s,

ef forts to control the accident. In order to assess the criticality hazard,.the re f ore,

.t is nccessarv that a b, v* :." C A5 N(

f u l l ana l y s i s o f t-ha 5 // p cs 3/e,,a v r:

criticality

-e a

b

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,_um M (7 'f I a d" ? -

The benchmark critical experiments used by Public Service Electric and Gas Campany to verify tte mathematical theory for calculating (Kerf) are not adequate to verifv the accuracy of the predicted (Kett) factor These expert-ments should only be considered as a means to develop the theory for design purposes. In thc final analysis, the loading of fuel assemblies inro the racks will be the prcof of the validity of the predictions o f IKeff}"

Therefore, it would be necessary to perform an experiment in which new fuel is placed in the s torage racks under controlled insertion and neutron monitoring for criti-cality. This should be a practical confirmatory experiment.

It is well-established that such an experiment is neces-sary. Also, consideration should be given to the question of whether local boiling in a number of spent fuel assem-blies could cause an increase tn

(.e t),

that is, whether y-the fuel in the storage tacks would be over-moderated.

In this regard the above descrined experiment snould inves-tigate the effect of voids arc water temcerature.

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s (a)

Severe reactor accidents are the ast l u e '. y cause of a,oss-ot-water i n c i c,e n t in a spent fue,t s t o ra;;e q;

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pool. A severe reactor accident could resu!t in such heavy radioactive cc.

iination in the area of the spent fuel storage pool and building that the entire operating crew would be forced to flee for their lives. Such high radiation levels would persist for months and thus would prevent emergency crews frcm returning to the spent fuel pool building co maintain the pool cooling system. In such an accident, it 's likely that the cooling system woula breakdown, due to a lack of maintenenace, which would lead to a rapid boil-of f of the pool water. In addition, the s pent fuel scorage pact for Unit No. 2 would suffer the same consequences.

Indeed, the Unit No. 2 reactor

(

would likely be abandoned as well, setting in motton a train c f events leading to a core meltdown and possible explosion in that reactor as well).

(b) there exists a great number--essentially an infinite number of severe reacter accident possibilities that could result in a loss-of-water incident in the spent fuel storage pool.

(c)

Severe reactor accident possibilities have F" I '

never been investigated ano.inalyzed by the Nuclear Regula-tory Commission and its Atcmic Safety and Licensing Board for the potentral consequences or the likelthecd cf such I.

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accidents, except to a limited degree in the Nuclear Regula-tory Commission's Reactor Safetv Study (Rasmussen Report),

which is not an adequate hazards' analysis to assess the eactor accident risks (see contention No. if)(6) below).

It is contended that it has not been ruled out by scien-tific concensus that the potenttal harmful consequences of a servere reactor accident causing radioactive contami-nation could be:

(l' 120,000 square miles o f land requiring evacuation or living restrictions.

(2)

A lethal range of seventy-five miles of a released radiation causing acute radiation disease.

(3) 500,000 square miles o f l and requ. ring agricultural restrictions due to the release and follout over the land of Strontium-90 alone; and (4)

If the living and agricultural restric-tions are relaxed substantially, about 100,000 to 500,000 additional cancer deaths could result. From the figures, it can 'oc appreciated that there exists the potential for causing abandonment of the spent fuel storage pocis

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blies to 1170 spent fuel assemblies, amounts to an eigh-teen-fold increase in the quantity of spent fuel and hence Strontium-90 and Cesium-137 radicactivitt to be stored. Since the core of one reactor wculd contain about 3.7 million curies of Strontium-90.hich, if released in a reactor accident, would have the notential for causing agricultural restrictions over 500,000 square miles, and

)(

since one storage pool would,by the preposed storage in-crease, contain forty-five million curies o f Strontium-90, or twelve times more Strontium-90 than in the core of the reactor, which could conceivably oe released into the atmosphere in a loss-of-water incident, it is imperative that the most likely causes of a loss-of-water incident in a s torage pool, namel;,, s e'c e r e reactor accident possi-I bilities; be investigated. Severe reactor accident possi-N bilities cannot be considered independent of spent fuel storage los s-o f-water a ccident s. From a radiological health s ta nd po i n t, and in view of the fact that Strontium-90, Cesium-137 and Plutonium are among the mest biologicall:-

~~hazardous radioactive substances,.i not the most hazardcus, l~~

50

~~'\\~~

~~the proposed storage increase would dreat! y inc rease the a~~

~~potential consequences o f reac tor accidents that the.ssue of the likelihocd of severe rea :cr accidents must be tho rough'. y and comple t ely inve s t iga t ed. iThe procosed~~

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storage increase is like proposing the construction of twenty-four large power reactors from a radiological haz-ards s ta nd po in t, particularly with respect to Strontium-90, Cesium-137, and Plutonium release potentials).

~~(e)~~

~~The Nuclea r Regula t ory Ccmmi s s ion ha s announc ed /"4 on January la, 1079 that it supports the "use of cr-"~~

~~L M~~

~~Pr o V.,bllis t ic 444s risk assessment in regulatory decision making," in b~~

other words, the making and considering estimates of the numerical probability of severe reactor accidents. However, it is contended that the probability of a severe reactor accident occurring within the next twenty years or so o c c ia'n' t

-/

~~which results in a loss-of-water i": !:st in a storage g~~

~~n af pools cannot be proven to be significantly less than 100%f r Y:b J.~~

~~'d tlC and that, therefore, y " M4+L ies risk assessment methods~~

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~~should not be used to assess the risks of the proposed storage increase.~~

~~It is contended tha t in o rder to sa f ely judge the Ff o e hazards~~

)(

~~cverall s a f e t :. of the Salem reactors and associated storage pools, the applicants lutility) and their nuclear plant Ccmmis-designers and supplier and/or the Nuclear Regulator-,~~

sion must analyze and evaluate all known accident possibilt-ties (sucn as multiple control red ejection accidents, including chain reaction ruptures o f centrol rod drive mechanism hcusings, loss-of-coolant accidents withcut SCRAM, ejection o f a high react iv. ty worth control rod, c

~~- i; JUV IJ:~~

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concentration in and power excursions with excess horon the coolant) f or both their likelihood cf occurrence and their potentral consequences, and publish che entire analy-sis and evaluation (that is, without reduction or simplifi-cation), as well as a reduced, simpli'.ed summary. Further-more, the Nuclear Regulatory Co.mi.ssion snould accept m

~~and hear testimony from all parties on the adequacy of such an analysis and evalur. tion, and should accept general testimony as to the likelihood and consequences o f all~~

~~-tee.fr.wnt/~~

~~possible seri ous reactor acc ident s (that is, the t: '. enny x~~

should not be limited to the scope of the applicant's present saf ety analyses or the analysis and evaluation called f or above, but receive independent analvsis as well), and shoule fully consfder and fully weigh all of the te s t imony and analyses and evaluations as above de-scribed in forming its opinion on the application. The called for analysis and evaluation of all possible acci-dent--their likelihoua and consequences--should also in-clude:

~~(1)~~

~~A listing of t'l theoret' cal uncertainties n th regarJ to the,assthilitv for worse conse-quences than predicted and the ccmbined effect of the uncertaint.es, (2)~~

~~An identifica r ;on o f all parts of the analyses which have net been experimenta..y i~~

~~b ' i.' I I~~

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~~ave verified.~~

~~(3)~~

~~A dc tailed fault tree graph for each accident possibility and a graph of -he chain of events and equipment f ailures and human errors for each accident possibility; and (4)~~

~~A compilation,f al experiences c f reac-tor equipment failures and human error related to each accident chain o f events.~~

~~It is further contendeci that a severe reactor acci-~~

~~.?.~~

~~e hL f)-~~

~~' 6~~

~~@l dent which would likely~~

~~- cause a loss-of-wate-~~

~~'e r t v.c 7~~

in a spent fuel storage pool is likely to occur--that is, such an accident can reasonnbly be excected--based on the fact that there is seemingly an infinite number of such accident possibilities, and based on the large potential for human error and carelessness and other human f a ilings, and en the experience record of equipment mal-functions, past reactor accidents, and near-accident inci-dents.

~~F2 (f)~~

~~The following addi Lonal contenttons regarding reacter accidents are offered:~~

~~(1)~~

~~The theoretical prediction., cf the ;aurse of the reactor design basis accidents have not been adequateiv ve-ified experimental'y.~~

~~The accidents o f ~cs t concern are the lo s s -o f-coci,nt accidents,~~

~~.he control cd ojection c 'iri 7;~~

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~~ppve accident, coolant cump seizure, control red withdrawal acc ident, and the anticipated transi-ents without SCRAM l ihat is,,:thout emergency fast shutdown o f the fissioning)~~

For examples of particulars, see The Accident Hazards Of Nuclear Power Planes by Richard E. Webb (L'nt-versity of Massachusetts, 1976), Chapter 4 and 9. The applicant's reactor safety at ; lysis reports do not give adequate scientific reasons why full-scale reactar tests are not necessarv, nor do the reports even acid ra w s the questica of the necessity of full-scale or even large--

~~but-less-than-full-scale tests.~~

~~(2)~~

~~The theoretical analyses of the design fq13 basis accidents have a number of theoretical and mathematical shortccmings. See examples in chapter four of The Accident Hazards of Suclear Power Plants.~~

~~(3)~~

~~The safety analysts reports submitted g;~~

~~by the appltcant do not justify the selection of the reactor design basis accidents relative to possicle accidents which are more severe.~~

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~~f:]1 (4)~~

The reactor design basis accidents are analyzed in the applicant's safety analysis report with the added assumption in some cases of a single additional f ailure of some compon-ent in the safety systems intended to control the accident. However, the applicant's and the Nuclear Regulatory Commission's a#alyses do not give adequate analysis and consideration of past reactor accidents and near-accident incidents, some or most of which occurred by and with multiple malfunctions and human error. This is further reason wny the full analysis and evaluation o f all accident possi bilities--their likelihced and potential conse-quences--should be prepared and considered.

The Suclear Regulatory Commission's " single failure criterion" to judge accidents worse than the design basis accident as " incredible" is wholly inadequate to assure safety, and should not be a basis to den;. the full investi-gaticn of all act: dent possinil. ties as called for abcve.

~~(5)~~

~~The magnitude of the potential consequen-Fi ces discuss:d abcVe requires that the Saciear Fegulatory Ccmmission should require the analy-7 ^~~

e

~~<? 9~~

p :L sis and evalua t ion o f the likelihood and poten-tial consequences of all accident possibill-ties, as described by the above contentions, and should fully consider and fully weigh the said likelincod and consequences of all accident possibilities, and should fully con-sider and fully weigh the said likelihood and consequences in the light of the experience of past reactor malfunction (see Accident Hazards generally, and chapters 5 and 6, includ-ing the section on Probabili ty o f Accident s,

~~pp. 96-98 and appendix 2, and the testimony by D.~~

~~Bridenbaugh, et al.,~~

~~before the Joint Committee on Atomic Energy of the U.~~

S.

~~Con-gress, Februarv IS, 1976, which suggest that the likelihood of such severe accidents is not remote and may be unacceptable). A sound, rational judgment of reactor safety is no:~~

~~possible without the full analysis and evalua-tion called for in the above contentions.~~

~~(6)~~

The Nuclear Regulatory Commission relies Fd on the before-mentioned Rasmussen Report and a review of that Report known as the Risk Assessment Review Crcuo Rerort (Lewis Report to judge that the risk to the public health 1,u 500 a

oc

~~prg and safety due to the accident possibilities which are more severe than the design ba s i s accidents is acceptably low and that the more severe accidents need not be further considered.~~

It is contended that the Rasmussen Report and the Lewis Report have fundamental short-comings which preclude their being used to establish the level of risk of the said severe accident possibility. See Accident Hazards, chapter six and appendix one, and the reviews of the Rasmussen Report by the United States Environmental Protection Agency, dated August, 1975 and June, 1976 (EPA-320/3-75-012 and EPA-520/3-76-009', for discussions of some of the shortccmings. For example, the mcst severe class of reactar accicents, namelv nuclear runaway, are not analyced for their likelihood and consequences in either the v'.

~~1 -~~
SIA Rasmussen report or the L.cwis ReYcrtl us, Other shortccmings of the Rasmussen Repcrt are: The report does not present the analysis of the probability of the severe accidents
}[
whichthereportfcensidered, such as transi-i ents-without-scram; rather the repcrt merely gives the results c f :he analysis perfcrmed i ~i 3!
by the Rasmussen etudy group, by the use of simplified, " reduced" fault trees, for example.
In one extremely important instance, at least, there is no fault tree given at all, specifical-ly, for the accident involving the failure of the recirculation pump trip safety action wtthout scram" during an " anticipated transient (though this is a boiling water reactor acci-dent, there likely are instances for the pres-surizco water reactor in the report as well, for I recall no fault tree t'or coolant pump siezure and control rod ejection accidents).
The public is being asked, therefore, to accept the results of the Rasmussen Report and the Lewis Report on faith. This prevents others from being able to adequately scrutinize the probability evaluation o f the Rasmussen Report for its accuracy, enmpketeness, anc validity of assumptions (explicit and implicit), which are mostly subjective. Moreover, tne simpi.fied analysis presented in the Rasmussen Repcrt contains symbols
.;h i ;h are not defined adecuate-ly for purposes o f examining the safety systems for their potential for, and the ;ikelihacd of, malfunction.
asJ I
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0$N Cverall, it is contended that the appli-cant's and the Nuclear Regulatory Commission's safety analysis reports are not an adequate basis for assessing the safety of the proposed Salem pressureized water reactor and its storage pools, and that the Rasmussen Report and the Lewis Report are not an adequate supplement to answer the concerns of these contentions.
FF]/
(7)
The reliability of the SCRAM system to control accidents has not been adequately demonstrated. (SCRAM means the rapid insertion of the reactor control rods, which shuts dewn the atomic reaction). No backup SCRAM system exists. The applicant has not adequately demon-strated that a backup scram system ts unneces-sary, inasmuch as the pressure surge of antici-pated transients without scram may be too high.
(3)
The integrity ei the reactor containment system under a design basis accident (loss-of-coolant) has not been ader;ua t el y confirmed experimentally. Full-scale tests appear to be necessarv.
(9)
The appplicant's design basis accident OI2 for the containment syster and the emergency c.. r.
i~q JUU lJ/
Fib core cooling system (ECCS) has not been shown to be the most likely f o rm c f a loss-of-coolant accident. Specifically, tho applicant bio not demonstrated that a loss-of-coolant acci-dent will not more likely occur as a result of a strong pressure surge transient. Stronger coolant pressures would produce stronger forces on the various ccmponents of the containment systems. As for the ECCS, a stronger coolant pressure may be the result of a transient that produces a hotter core at the time of the coolant system rupture. The ECCS is not designed to control the higher pressure and hotter core (higher temperatures) of such
~~\\'~~
y a loss of coolant accident.
(10) It is contended that there should be additional consideration of an earthquake producing a loss-of-coolant accident, inasmuch as a prototype reactor plant will not 'c e proof tested by simulated earthquakes (due to obvious impracticality).
(11) It is contended that the spontaneous Pfj.
reactor vessel rupture type of accident and a vessel rupture due to pressure surges of anticipated transients without scra.m have o
L 9 n;g ps;ui has be n 4w onst r a t M' gY g4 pg(qu?
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fe? N'lG S
reacter a rce reue-
'A f/
e not been adequately demonstrated to be of negligible probability (to warrant their ne-glect in the reactor containment design).
There is the question of no leak-before-break warning.
(12) The applicant.'s safety ana'ysis has not given adequate consideration for the possi-bility, perhaps the likely possibility, that a severe reactor accident will occur as a result of unforseen causes o r e f fects, as that seems to be the experience of accidents or near-accidents in nuclear power plants.
(13) The applicant's safety analyses have given inadequate consider it ion to the possi-bi l i t :- o f c mon-mde type failures in the cociant piping and the emergency core cooling system piping, especially the possibiltty for sequential failure of the latter cue to the forces generated by the former.
(14) the applicant has given i nad equa *.c cc n s id '
eration Lo the pOasihLlity o f 5.'i b o t a g e, [cr e:< ample, consideration should be given to the lack of provisicn for separate r oo.m s a nc' blast shielding in between, to separate b a c.< u p saf et - systems, instr ncntation.,, n d cables io}
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from primary equipment in rooms normally un-attended, to minimize the likelihood of a saboteur's bomb knocking out primary and back-up safety equipment at once. Also, a multiple contcol rod ejection accident could easily be caused by a saboteur's bomb.
(15) Amplification o f the preceding contention along with supporting arguments and information are given in the following documents, which have never been disputed by the Nuclear Regula-tory Commission:
a.
The Accident Hazards
__f Suclear O
Power Plants, R.
E. We :;b.
b.
Memorandum in support of the conten-tion of the Canli tion for Safe Energy in the construction permit hearings for the proposed Erie pressurized water reac-tor (Docket No. STN-50-580 and 581),
dated September 26. 1977 which treats issues enncerning the emergency core cooling system: specific possibilities of "anticinated transients without scram" and their li<elihoco, the need for full scale testing cf analyses of certain accidents; kinds and causes of multiple y
r-s control rod ejection accidents' power excursions with excessive boron concentra-tion in the ccolant; loss-of-coolant accidents without scram; and common mode failures in coolant piping and emergency core coolant piping in loss-of-coolant accidents
=
c.
Remarks by R E. Webb be f ore the (21 Nuclear Regulatory Commission's Atomic Safety and 1.icensing Board on the said Eric proceeding. July 25, 1977, Transcript pages31-176, defending his contention.
d.
Petition to Congress " Calling for a Full Review and Investiga:Lon of the Hazards o f Nuclear Power Plants and Radio-active Waste Disposal," by R.
E. W e'o b,
May 20, 1978, including an appendix tic'ed
" Remarks on the Crucial Factor of the Surface Centamination '. im i t s for Plutonium and Strontium-90 "
3.
PERMANENT SPrNT FUEL REPos.
m: AT sal.EM F21&
'ai It is contended that it is &ikel, that the spent fuel frcm the Salem reactors will be stored per a-nently in the en-site storage cools--that the Salem reactor site will heccme a permanent r e p o s i '. a r v for -he high '.e/ei sad dI2
1 r
4 radioactive, spent fuci generated at the pl ant.
(b)
There presently exists no geologic nuclear waste repository for disposing of the spent nuclear fuel, and no such repository is likely to be developed and demon-strated to be safe, or permi ted to be built and operated.
(c)
Off-site spent fuel storage pools which store only aged spc.it fuel assemblics (older than six months or a year) have catastrophic los s-o f-water accident possi-bilitics as well as the reac:or s ;te s torage pools. Such off-site pools have yet to be evaluated fully for their spent fuel heatup and radioactivity release potential in loss-of-water accident. Furthermore, the theoretical deficiencies in Sandia's mathemat; cal theory (SFUEL) for spent fuel heatup in a los s-o f-wa t e r a cc ident, which are discussed in contention no. 2.!o) above, may very well mean that the heatup predictions presented in the Sandia Report for off-site pools may he grossly in error in the unsafe direction. Therefore, off-site storage pools cannot be considered a safe altcrnative for storing Salem spent fuci, nor does it appear to be an economically viable alternat;ve.
(d)
Even if the spent fuel were not atlowed to jq)g p accumulate in the Salem pools, there will be at least sixty-fice new spent fuel assemblies stored in each poci at any one time, wnich means that there would be aoout r ; ri 1 '/ /
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4 2.5 million curies o f St ront ium-90 in each s tora ge pool (and a like amount of Cesium-137). Information recently developed about the los s-o f-wa t e r a ccident hazards of spent fuel storage pools rev als that i r.
is conceivable that the Strontium-90 and Cesium-137 could be released
/
Tuck from the fuel into the cutstde 1tmosphere in -heen an accident (even for open, low density storage racks). Thus, a los s--o f-wa t e r a cc i dent in a single spent fuel pool could
.6 result in ruining agricultureg, over a land area equal to three times the size of New Jersey, among other disas-crous consequences. The cambincd cc. ca se o f radioac t iv:.t y from a reactor acttdent and two spent tuel storage pools (as a consequence of a reactor accident) would be about three times worse, fe)
The only way to avoid the risks of spent fuel 4 cy te l,\\
s to ra ge,,i s to cease generating the radioactivity by closing s
down the station and terminating the construction of Unit II--that is, to revoke the reactor licenses.
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Intracticality of Theoretical Analysis and -xperimental Verification.
The preceding contentions describe a broad scope of theo ret ic 9 '
.ral/ses and experiments that would be necessary in _
er co fully evaluate the hazards of spent fuel storage (and reactor accid ents).
Mowever, it is c ontended that it is not practical (humanly possible) to prepare the needed analyses nor to conduct the needed experiments; and, the refo re,
the full hazards could never be scientifically established, except by assuming the worst conceivable censequences--that is, a near full release of radioactivity from the storage pool.
[g p
/z9, T4 CO:,CLUSION Spent fuel storage at Salem (and any other reac to rs )
is unsafe because les s-o f-wa t e r ac c ident s are possible anc because the potential harmful consequert es are extreme.
4 Closing down the reactor' is the only responsible course of action. This would eliminate the risk of reactor acci-
!cnts, which itself is extremelv grave.
f a ud a ll 0 th er nu c /Mr pow e r p/ou ts W
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