ML19259B912
| ML19259B912 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 03/29/1979 |
| From: | Onsdorf K, Van Ness S NEW JERSEY, STATE OF |
| To: | |
| References | |
| NUDOCS 7906010099 | |
| Download: ML19259B912 (30) | |
Text
_
q,
,w i
//
q$T p
~4
~
Titts DOCUMEtiT C0tlTAltlSu' s swEsoF m m 0g Ng 2p P00R QUAUTY PAGES g &i v*
Nummt REwLumy ccm.mro.s y
3 i: thc \\'atter of
)
Q)
)
l',M.!C SfiW!CL ELECTRIC G GAS
)
Decket No. 50-2'2 C..T.'C.^Y, et al.,
)
(Proposed Issuance of kund. ent
)
to Facility Goerating License (Salen t uclenr Cor. elating Station,
)
No. DPR-70)
Unit 1)
)
D.~I F"EvjRS, C0!.E.'!\\SS ', S'E3Dl!AN!??! IN OPNSITION TO 'il'E l.ICENSEE'S.'DTION FOR SLC S\\RY DISPOSlTIGN INTERVil.';0RS' SIWlENENT OF mTERIAI. FACTS IN DIS!UE PEREAINI G TO CuNTiXiION T,l0.
2.
The licensee has git en iraucquate eerside ration to the occurrence of accidental criticality du' to the increased den,i ty or c maction of the noent fuel as se61ie<..\\dditional.
? r ttion of criticalit'.
is required due to the fol v.
.g :
A.
de terioration of the neut ron ;Usorbtion material prortded by the P. oral plates locat cd bet;.een the spent fuel bund!c.s; B.
deterioration of the rad structure leading to failure of the rack and coaSequent dislodging of spent fuel hu..dles.
For its convenience, P.S.I'.GG. has chaosan to lu a, together its c.. 3 : darat i' n o f the ColeumS ' Contentions c..a o c S ; :.
i ne.,u <epara te safett L 4 ;US, h 0.JV c i, are tCO ir.!DOrlant to he g'assed oVer '. i th Such SiiDerf;Clal
!!"' 9 t,
!he Colt.'anS ' SeCbnd COM' '.'t i ?:1 \\ ils dil2CtlV.. i th E!'e inc re. 2d
- 's'I. r
- t l ' [ :1C s'idt 1 t i a l C r [ t i t'a l i !'
ot'O :rT ' ' i: *ht 9;c10 tuel pCol du-1J
',il'
'[:0" ei the neut
- n!' ' Stien ~.'r
'. u r r.
a !
the I'c: c ! pla t _s d ts e I'l:1G.i ; I "'. i 1G' II I CIJ3c; tj w i. lit p r?ViO. c I X.f,
'l
'a
'04t
[jU'.i,'..h.
. ;3,,,
fl.O__
V ^ GY lqjDW,$}&P s I
'1 L
l 2288 ;53 m6 o l N m
m usage i:. t!.c nuclear irN trv.*
Accordingly, the stat e.nent on the si xth
.ge of licensee's nemorando in su; mort of its r.ution, to wit: "untr adicated'
^ainless steel fixtures have been exposed in pools up to 20 years and Zircaloy clad spent fuel has been successful' stored in pool for up to 18 years withcut mdence of degradation," is a com.plete non sequitur.
Interrenors in this proceeding are not ennosing storage of spent fuct in water cooled basins situated adjacent to a nuclear generating station situated near the Philadelphia netropolitan area.
Rather, they are strenuously Ajecting to the density of such unnrecedented long tern basin storage at this locatica uith an untried systea that entails a known potential for rack d; '.erio rat ion. :*
In this case, past experWce with 1cw dausity storage provider, t e rv little assurance of hieh density pool safety, o
Furthermore, what experience there has been t:ith spent fuel pcol storage in conjunction with nucicar pg.aer plant operations is not reassuring. /cs stated in the Minor affidavit attached hereto the "enticello and Connecticut Ya:d:ce
- eac e, experienced rack degradation. (Minor, page 5,B). '!he relevance of these rai integrity de ficienci.es, while disputed by P.S.E.5G., is clearly an unresalved factual issue material to che Colcaans' contenti.ca two.
Finally, the verv report relied upon the licensee: "Echavior of Spent
'. clear Fuel in Water Pool Storage," B.9iL-2256 Battelle '? ortho.est Laboratories, acnterher l'.q^** details the known corre, ion probiers which have G W If !? l f lih k MqNJN=
- "The present rack design has a acninal centt 6 oatettter'spriding between fuel starage cavities of 21 incnas, tne proposed new snent fuel racks would be udalar r.tainless stell structures with individual ;torage cavitic.; to provit'e a ncatc.a1 cente r-to-es.nte r spaci ng of 10.5 ! aches." NE Staff Safety Livaluation, Januarv 15, I M Sectien 1.n, page 1-1, "aragra"h 2.
'ihis '3C Safetv and Licer.sino Soard can t Jse judicial notie of th Ja;r t;nt neat o ht, at..'i c water om tic.e indu os corrosion in ne ale, inci: n sta m ess r
s 4:cel.
The '.A Staff Safe n cv t!uation es t imates th :t:"Le
- tx1, inct.
_N Nat laads that uilt be aJI?d M increuing "the ntder of spent ft.21 as ss:"
x n the Sh' tro, 203 to 1170 9:'11 be 1.3 x 10 B ru/hr." Renc r t ret e24, St tL, s
.., paragcapa I,tco.
- Since P.S.E.6G. 's nation u.:d supporting doeur its attached thereto onb. th:- first icur pages of the Battelle Pe!' ort,, page thirtv-< ix of this report is att acNl ' ere-to 23 exhihtt
.1.
2288
.:54
alreadi oce:rred in spent fuel pool storage cells:
"Altrunt= corrosion behavior has been substandard in some borated pools.
. Considerable altninua corrosion also occurred in crevices on the cannis ters, perhaps due to o:ygen concentration cella."
'the unfortunate circumstance that the Battelle Report can only speculate on the cause of the corrosion as being the result of oxvgen concentratica ec113 r.erely add 3 to the unresolved safety issucs pertaining to long tem basin storage.
In terreno rs intend to fully examine both the NRC and P.S.E.6G. '.titnesses concern-ing these corrosion risks at the Salen hearings in May.
((&]Q'[}{\\
2288
.,55 e
_3
":TE J,lLNORS' STKlE.'4F..NT OF t'RTEPJAL FACTS
_1.' DISPbTF PalTAl.'UNG TO CONTF.NTHU: SIX 6.
The licensee has given inadequate consideration to qualification and testing of Boral uatorial in the environment of protracted associatica.ith spent nuclear fuel, in order to validato its continued properties for reactivity control and integrity.
The ntrerous unresolved safety issues nertainino, to this contention are bcst exemplified by the licensee's anonolous argtrent that the greates t care passible nas been taken to protect the Doral fron exposure to me spent fu21 pool
' uter environmen* while proposing under certain circtestances to dose this Boral with conta:ainated pool water. When a leaking problem arises in the stainless stcel shroud, P.S.E.6G. intends co drill vent holes in the top of the storage c 11 to relieve the gas pressure buildup inside. This intentional breaching the integrity of the Boral protective shielding demands the utmost scruttrv to determine all the consequences of action which, on its face,apnears to severely u durine the very design basis fer the safety analysis of the spent fuel neol.
bxples of specific factual questions pertaining to the nature of this venting nrocedure abound: ', hat equipnent will be used to drill these vent holes?, v. hat ci ne holes are contemplated?, how long will the cells be used with vent holes?
Dat safeguards will be used to ensure that the holes are drilled no further than requi red to relieve the gas pressure buildep? In sum, no detail is givm' on the proposed method of relieving the gas pressure thru venting without doir.g
.'.di tional damage to this safety systen.
3!creover, the uncertaintics of so-called nomal storaga operations are visa fertile areas for factual inquig b'. this Board.
P.S.3.6G. has s t:ted that
. : esen t N' C plaa t opera ti va l ien 3e pe r"i b cen tinuces use o f the d
,e, '
't 1
- N aparaxima tely 40 years t e; alsc. use beyu.'l thi.s i
val far the life o f the olent,
period is even contemplated (See Transcript, Prebe;.rtng Canference, Mar 18, hQ; 2288 356
n -le to i03-o.
D': spi te tnis ve:v reai po:ss i bili t>
that fuct asse::.h ' ies '.111 ke; in the Salen pools at Icast for seventeen years (dua solely to econenic cor.siderations since viable alternatives co.. exist), the '21C S taff Sa fe t" Pc,a r t
<tates:
"Since the possibility of long-tem storage of spent fuel exis ts, the effects of the poal envirortent en the racks, fuel cladding and pool linar are under continued investigation."
NRC Staf f Safety Evaluation page 2-14, Section 2.4.1, paragraph Two.
This candid acla:c.iladgenent by Staff that the P.S.E.6G. plan involves rany facets still being evaluated itself underscores the necessity of exard ning these issacs at a plenary hearing prior to authorizing rcracking which ruf e.. nase the public ur.kncwingly to unreasonable risks.
2288 257 k
e.
3e
I.'. iER'.li':0R5 ' STAT E* E'T OF.' L3li SRI..L FACTS IN DISPLTE PEIHAIND.C FO C01ENTION ':i:.Ii 9.
'Inc Licensee has given inadequate ccasideration to altornatives to the propo';ed action.
In particular, the Licensee has not adequately evaluated alterr.atives associated t.ith the Nuclear Regulatory Cocnission adopting the "no ati. ion" alternative for licensee's application, which would inplicate the follew'utg:
A.
expansion of spent fuel s torage capacity at reprocessing plants,
B.
licensing of independent spent fuel storage ins tallations ;
C.
storage of spent fuel fron Salen ':o. I at the puols of other reactors; D.
ordering the generation of spent fuel to be s topped or rest.cted (leading to the slow-down or tetuination of nuclear power production until ultiaate disposition can be ef fectuated).
Tha' material f" cts exis t concerning alternatives to the proposed risky e nansion of the Salen One and Two Spent Fuel Pools can r.ot be seriously questioned.
':or has i'.S.E.S.G. really atterpted to do so.
In its Statecent of Undisputed Facts, P.S.E.6.G. has included the following points:
34 It is highlv unlikely that an Independent Spent Fuel Storage Installation ("ISESI") could be available to accept fuet v 1933 0: 1984. (e: phasis added).
It is unlikelv that the Hope Creek units waald be suffictently cenplete to enable fuel to be stored prior to the uncodified Salem unit fuel pool heing fuel.
(er.phas is ads'ed).
Of course, were this Boar:i to deny Public Sercice's ap,lication to ex;
- d Salen Pools f or any one of the. afety or eavi ronnental co ; erns cldresn.
- eLein, Ue Ca;l F0st as3ulc.. Ihlt the ((ke1ih003 of th2 Ce N ?.V e.\\Tcditing the 2288 ;58
.ns tn:.:t i ;u dt;dah for u'.u Hopa Creek paais u nh' undu3tedly be c.a:n greater.
Thi.; 2s particularly so in ligh t tf the cost of shutting do,en Salem One, es timated
- c P.S. I!. a.G. at < 300,003.00 per da:.'.
Further-' ore, the unse:tled posture of "lSFSI" availabi.11ty is subject ta re.pid chan g.
Within this past weck, the h York Times reported that the United S tates L'e,artment of Enero.v. had reached an anreerent in principle with the State 1
m a
of New York regarding the reopening of the West Valley, New York speat fuel s to rage fac i l i ty. (N. Y. Ti mes, p. 1, March 21, 19 79, Exhibit D). No one can uke the categorical statement that an ISFSI will not he a' callable b. the tim 2 that Salcn One and Two uill reach pool capacity (no sooner th:m late 1983 if no unusual da.vn tii.".e is experienced at either niant; a highly unlikely eventuality).
To do so is pure speculation, upon which a totion for sumary dispcsition can not
' granted. Mississippi Power and Licht Cemnany (Grand Gulf Nuclear Statica, Units 1 and 2), ALAB-130, O AEC 423, 424-425 (1973).
)The SRC Staff Eavironmental Irpact.np raisal, Januarv 15, 1979, Section ~.3 page 16, paragrapa 3 s tates that the U.S. Lepartment of Energy announced in Octcher of 1977 its plan to provide interin fuel storage facilities by 1933 or 1954.
For some unu.mlai.ned reasca, the staff has decided to discount the arce.1 comit-nent of a Cahiret level Deparment of the Uai ted States Covernment. This ca: '::e:
t reat,ent of a major national initiative unrra tts a thorough review at ' p'ena M arire.
creover, P.S.E.5C. has stated withcut clari;:catien that : "(s)ince Ralt s Unit 2 t
is expected to begin operation shortly,[ Salem Una has been ope rating for crec 1 year no., and will need to refuel within a few '.cekO und will have a
.a araw d ; char:
of fuel, both unenlarged fuel y'als ';ould be full by 19S3 cre:'
- the c:qaei n of the poc1.; we re sha red join tly."
This i.dentical deadline fo: actF niants et w no al10. ance for the edditienal vem before Salect Two :.01 c ~1 to n f f-lo.u! i t s fi. rs t 1/ 3 o f a co re.
Interv.. ice, ninn ta full', exnlo';c all these fac!Ual Lc w as a t the hear i r.; sci 1Jt..;le d fD'
- 2. 1979.
2288 59 e
f*
IN1ERVi:.T:S' 5TAirmir 01:.' LITER [AL FACTS IN DiSPlfit PERI'AI"ING TO CONTE' TION THIRTEEN __
13.
'Ihe licem:ee has failed to give aaquate consideration to the cumulati re impacts of expand-in", spent fuel storage at Salen Nuclear Cencrating Station Unit 1 in association with the recently filec proposed arend.ent to the application for an operating license at the sister unit, Salen Unit 2.
(See A;r.en&:ent No. 42, Docket No. 50-311, filed Anril 12, 197S which proposes modifications of spent fuel s torage which the interrenor believes are siniiar in scope to the Salen Unit I application.). For exa ple, the licensee assur.es an increase in relcaacs of Kr-85 by a factor of 4.5--
due to the factor of 4.5 increase in spent fual (licensce's application, at 10). A sinilar increase, absent exceptional controls, can be expected at Salen No. 2, rer.u1 ting in a ctnulative increase in Kr-85 cmissions 1,y a factor of 9--almost a full order of nagnitude increase.
(If similar spent fuel increases are postulated for the conpanion units, Hope Creek l and 2, now under construction, the cunulative increase could rise by a factor of IS, or alnos t two full orders of magni tude.)
In additian to the nurerous factual issues associated.eith the need for faultless operation of the Salen Une and Salen' Two spent fuci pools over a 1cag r e riod of time (See Minor affidavit, p;'ges eight through ten), the Colenans' Coatention 13 is wholly ni.sconstrued by P.S.E.6G. in order to avoid the fundaantal policy thrus t of 10 C.F.R. Part 50, Appendix I, and 10 C.F.R. fi20.1.
Purstrm t to
- 10 latter NRC regu'ation, P.S.E.GG. is requi red to:
...nake everv re.uonable ef fort to naintain radiation exposures, and releases of radicactive caterials in effluents to unrestricted areas, as low a3 is reasonable achievable." 10 C.F.R.
$520. l.
This rule, then, clearly obligat.x the licensee to :.,e everv reuscas ie ciloct to riaintain rautation e3posures as low as is reasonable ach tevaSle i.r
'.i n.
ali decis tons on niant crerational mades aid not nerely relimte upon the dNilt iir; CCit t:lilE.ca t E CCI JnisT.s s nCD it hb :! ras tiCally ' nCrerded t '.J T:blai t ica I
2288
- 60 m
-S-
lead in the spent fue] paal.
Having nada a decir. ion to increase tiv public's e.. pus u r.
70 radia tion, !'ublic Service is ud:t:r an affir atie duty to 2 stab'.tsh the re.ue:r.blerass of thts act ion in liy,ht of alternatives that i.ould r.ot ential
- uch.icreased exposure.
If not by imple.nenting addi tional containment m:asures, tire licenste cust seek to achieve this standard hv ado.otina alternatives to the a
proposed action which do not result increased radiation exposure.
Therefore, the factual basis for P.S.E.fM.'s conclusica that increasing tb public's exposure to Krypton-33 radiation in the entire Salca region ccastitutes ccq31iance i. ith 10 C.F.R. Part 50, Appendix I is an issue which can only be re-solved at the plenary hearing scheduled in this r'atter.
P.S.E.GC. hereby sceks ic'ernissible to obtain bath a shield and s:scra fren the
.x.w regulations and rulings pertaining to this proceeding.
?. hen intenvaars 4 sert that cons tcration be givea to the ac+,aacy of tue spent fual paci coatlin-in ar u.11ah of the incre:ued ris! ; posed b:. htgh density stm c.e, they rre told th:lt this has been foreclosed by the prior e, rant of an cperatien litense to '
ti. ' plant, bilich Jo:ind th i s E n::ture to be adequate.
'.hte thel e s s,..;1en con -~3n ted,
n th th<' obl !?ntion ta matnt:ti a radiJ t ion ev'u inre a.s lcw as r^aso: Oiy achi n ' Ole,0D0
! ( Je!,
.-e p repas ;:; OC ' J's0.'o
.urtha r e fforts v:ha tsoJeer, except to ceia: e the lilJ t eas0d e.\\:')sMr0 10 De !!U i,1!flC;Utt.
I n ? ' n JIP.'rs Os "etll![I' s L '; '. i
!'.! (I:2 ' ik l':LI R. D il a t C C'? (I'l.
le;t'
' ' ?.,ja N
[.ll-r, s.' a t i ' '1 1.
U I.J _ ' ;d [V itCaie';dle Q as! I EU ' ?s JJ 1 di
'Cil.J C
- t
- 1(
- 1'.,ttiVe JJ7 ion 5.h iL.' Cin
.t ih t ',.h ' O
- 3 l)Ils Ii '. I C "
- 0...
O ',1!!:i1( c, f or all Se foregoi n;; re n,an:,, the lict.n:;ce's irn t ion for si::! nary di m.as ition
+,u1 J i)e cc.)id. i.i.
Itespectfully st6aitted, STANLEY C. V.\\N NESS, Puis!,IC /d)OCATli
,,//
( /..
>((
lgy. w
__ _ ___ n,L i ii lil 1;l A. O.'n,i C,iWP,
E' Attonley Cor Inte rcenori, lo-
- fe r
J I d; 3' ci e '.
j d v v h i:J ts
.n J
3 7 r g i. ( p r '.
.. _. I..
ur s-r
.i m --
-. U.
i l.
% t n n,, -!. U. ;..N,', (-.
2,, n i s ;a ls L L4
't 1.jd V,; w.
- j
.,,,.,-.an
~-..'.,m y
.i s
a f
.c c,
. a ;. i c..;,
+
s.
0"dau--I c.. rom % <e M i
e
' w :,-
w w,.r--
t J
- j
_,W,."'if,U,MCfM3IfJI9 i a U ninmir.-er, u,r.r._ m w' I
- g. :..
.. e i -
-F
-4 M:V9 ;' M 'M1 ?.* d S C S c;.
- .nr Va Pr. Su -.ad '.7. ranche$, I 3.
.M r
~
',l @-(,d in ' Var' %i 'y 1
.*\\
E ar: 90 m:11 ion cucie ;_ t 7t gw.gy,g y7 L t,~,'.v*c a
..~ :n tetive
.n,a" - ra gs, c ctni 4.
h-'* 9,r s N i
d* u laMrata-v an.mi; a; d c.ee. na. : j7
- ~ ' ' "
2 4
Jy 5TEVEN.t. WEI3M.\\N
!&1 Sat nad :.--n ex::oset o Lravs.
i ~
iI
- .,e+. &
~ ~ r. m *.
e
.-wetw--en %
c-ntly. 3 dm.ll! hole wu d;scov=r.d i t-
'GMINGTON. ?.tarea :D - Arar j in a Catchga, lym< benea tra ander. l !
ran a year of negot:at:on3, the
- 4'olndtan4 holctng Me iiquid us* *, Ind I s._.,
u M" W *- d emu >
. -ni Ener77 Cao arme '.t :us :en:a-l Le cate order =d.N:c!?ar.% sernces !
r it imme::a:e y as a p.yan-21 f Mr. Sc lesinar " vu x m 3 ym a -
to rap
? y gred :o 2ccapc resanstality --
. nmde ec>t of :evani rundrad m:1 53N 'am1. 3 <1us+ Se agra c nt '. mcVeenit then?
.ma0 far evan:uai cispesai.mt..
n the Fedenl Gov== ment duc!cmi
' II815 Cr>w. nd lt *vo. lid !.n3 o ha r n
.h : -w York 3 rate m hwe cecos.ta ui:
bDY 03DN *ake ei?ct antti sor-cme t3 tow due aporac:atier.,- ;ag 7,g t- [ly radioac*1Va "t:clede tv95te at *ne f
' Of *TIr". the ACord /.ces not i%en 2 T 9'2nr
'
- N S * * *S M 2 N eS-
! [_, lf.o,j' %...$a
%+y. N Y..
tor 12e facutty near.
t ;2.nzards pose.1 by Se Iea < or N need
. i,'a M[au. 7f--..Ja? 2m?
i t3 repair:t, accorceg :o state eHic:23.
u y ila.
i
're same em ce Carey adetrus-i Under extatmg armngemerts, the !': crL John M. :ert. acQh3 g".}M u.
tr "un has gr-d to acceot umt:cnai) euct nature of te state ;ove==ent>;
secr?tary :or acerce :.=ch; c.ngy, e de.
- qu of nuc:e.tr vute. prcduced ay) rst. ors;5ility ice WC '/ alley is ut dis-CI'U"I to COCmem av:nz b N-e me citeron cremung attund Newj FMe, and Govar or Car *y i as b *- n arass.
Fotr*ss" had =c;-nt.y hn - are..: re,
'M
" ? f':bWns.
c, Srate. for mterm stony at Westi i: Z Ue Stat
- Enar3y Commusica.er.
%y until the F +f atal Govar' ment '
hmes L. Lacccca, to reach an azp AccoM Coven C:ewup Co<t 4 e c -s.;p with i ;org-aw uted pian for ment f>r ta Fa.i+ cal Govemmant o fr*.
.C*rer3 zugested mat 7=d.nl rer2.-
ul aisresai t m *u.
I cmenh did nor w*nt co M et. ?ir W.
M e1 vord ; tot cut tMay thR Mr., (m Car'.:3ccori 2; c m'.,oien 5.-ca;3e.f pretimmar/ 32menent wtw aa".
a,hleeinpr ind Mr i
y Larc 'ca 5 d;tnen w
.3 w i...q.
c.S= cf 2.hn-
' - _ wrrt iecrenev,.ames R. Senes-S. "3 N" W*"O M *d :.he"wnt ar.t 2u m ta 2.ce 3, 2-
[3[3 7? & tans rem ucig ro ;-. i c.ar*.i te m w2m ton ;r c-m'.;. 7 s,..
- Ot' e 3t r e [>vamment, must N r
c,1 or J ael 3
, c :'v/nl Gcvyrn-
- q. w3.;, ~-.
mm oy the 'inits Buse and Cen.
' " ' ' m,-.)
n 1
n.
.,. [cy 1:b n, g.,eme,; q g ! yeari; 4
r *. i t e.orta it can ca.(e eif*c!.,ut cf adW YJN. d!$c!rNdd that h hj ;..f
.O (4sc :
V'ad,.,135urancas.;em.a time agg f7Eg Mt %y Sngygg3 7;, g;,
yf JIIIc 3l3, Iho d:3C!csed "iM 4CCortl C
ed ty said it constnut d an mpor act
..te. pcausmt-r on WN '/aliey.
l n, t:3. tne Sch!=v e rT.ar. ; w.
e-wrown an cre ot Wa iarest point.s
, a ya.tr and a Sif ago, acc~ary, meet wid can Mr - e me-.aj c.;y,,,-..
'*en:10n Nt% en. Winy and he
. Onfir?*r 3nd I reiche } an q;.ac e,og { m-nt to 3Mume aln's g d tM W Cf L*-
c-In prmet pie tnat tne Facent c-.ivemment : ;csm? ol de h p: :-v.:. in c e.
crett Gov =rnment.
3 i; The /0.tf0 m m af, v w. g w.,
s
- Tdd ?V"nMaily h.uma r-R Mrmaaisin3 Qr90 4rr/ D*lunct to,. th gggy.g gg g.5Corigg q. it,f :
i
- ggy. y{
mue in tne wm-times bitter ts0u:e gnd M.uld under*aks to remove inern.7*' ces3. For +xamo;e, t Eni;I:en ue5cn-
-' e O funct saMacn New Y0rA Ni1C. ear
- *NVniaan 3 aid. '-Last Wa*k he caiW.I iIr3tif n pniact 'O f Suc.h 2 t= c n M
! * !J T0rm m* tat t. :3 w*ek he wculd ; h7,b. Mdme. 2 Jam sto v, 0-mn r.= ~an t* Su -
,3 7
ecca t'anter, a m eailed"r-mcerina M
NI*"*J "O E2U
- ty' en ! 3..Wicr= ute >outretsc cf Ihe SeNa f or WM5 r*!*."*'nq t3 @a 7 =d. l,n. L.in gr*ss. w
- t-a. ~.s 3, p
,3C,.4a.
i i
sndc r.er?'r Carp r,-""a--
,1 0
.f
.3 tra. fly *I 3f !!S.Cnd Cr3I JNC3 vf 343n14mm an ard h'u',
-e " nmi ' n 2 '.. ~ a nt
. i-d m 3ay on me y,.'yl rited 3tatn.mder whch 'vnnJd w
~
~
ava
? rOmmerC313CaOLC *s.
taj of jnv such afday gj.;m3;.3
,.g..g l PEN *CE!3'*nating ind r!+cemmis.!
'9:cc(,m.n.
'a
- . tnt. ov e.1 Ov tte
- e. tate and,
,***v'n"f=m m 4
U$,t
.-d, weiue : M sar. cu. i e-;
. 5HI:en cevrcm en ' -..'
% J mm
.a.f di*he Gat"/ dl dmpisay. #t5 3 N p.3. w r.c. g, y 4 y
{;
erM pm;ect of u v. y.
n
,almn A. Rec.<e-
,..,,,.., g y 9 n y g
- n >J. At 2 ame of 12n hec *3 Cr r
ma.it mth Mr. 3cnlest.Tr becaur.e I
a
,/
- Jc, Y
k ar* f nu:! ear power. It vu Jaut
,-e
-*.. 30, in AC L".UW" t zed sy"'Delt Ot Wg ms*
- l#
. Gr? of ine nAunW3 ***r?f ^ a -
yy sai vt ne paciem al nuc e i s/
Vb
- '..j 74 3*d i.
- a1.a V?ar..no 'a r**v d-g Q\\/
g n ' '-* 114 ' -aq ' * -"* ? 4.le!.'. a i ca. s.- q q r 9.gr e ;
-*,.-a D
. e nem tr m na:
.o :-m j
C3
- nat n-ce
.5
- rutr:vv 1.
- cs.z i mine f elt 3 4 A.wnJie '.eai
- n.M Z-I,L'110 t t
.3 s
- :c r-arSv raw.en:3.
ye maiy rad.cacave mater.ai at' V 11MV C0fMisc3 Of IM 'On3 Oli
- v. t' at used-ep ue: ear 'uei rods in i
'n 2* mis: I.M. W C*aD!C I?*t 0f soild l
- I. [rmar'!?.*NV*r cardWTr?. And. i
- n ne mest :a;ar::cus Ju stare.*J o taden3.,f T:iniv nd cac::v. '.q-i
- i..
. -.i
.ti 2
3
..,, y--
..f.
u.
-,e 4
a.->
t,.
a.r.,,.,
s s
.., i
...,...3.:<
.- I:.-
-.?.
- c. :. c,.. : -.
s 3~...r.,
,: )
...i.
.?
. s,
...2...
... ;; ;,2 aLi.
-j i..
i.
44
.-J.,. :
"c
..n.
a 4
c'.-
~ si
_.. - h y w.
n.. r..-
-n
.'.'.*...8I 2
u.*'.a
..1..
.S.".'..<^...-
.-r-.-.*s'.a.
s.ri
.t e
- =ru
- ,. a. '.
L g
.s
... : _ C.,.,. e.
T
~u v
2
- a p m.. L.. w.~ ' - + -,
'3-
_ _I 1. _..,. e f. i.,__-..L.~.a._u_.._%_ _ _ _ _ -.
. _ _ _ _ _ _ ' _.. ; 3
_. __ _ _ _M _ _r 2. 1-~'_..;.-
m
.o
..A
... i a
i
. T. g...a.
. m
, <. ~..
z.
g1 i. *
.-..iG C 2
- 2..i v,.-
. i.... ;. t -
. t.,n a --- ---i.. 2. a.2. c.m,, *. s, 5
m.o n..e s/ 7 a
t a
i n.
3 s
L, L.,0
.31,
<,.., w,.r, - u.!
u,n - i.
F,. n_
b 3.
i.....
i....< -
}a. 2 _,1 a. i-2
,..w n.,..,.,.- - - - - - -
c.
vs.
2.
..t u.
v3 A '., n. e > ;i :i.:,:. - - c M. a'i
'! l ;.,,
c,.,.. n 's } 0., 0 -.
L;,,s a. -i., -
2_. _ _.a_.:. _.3 2,.l *
I___U_1 p. s c. us.aj_..
J-
.s
.a_ &. l..
L.... c. 3,..
- t. i i a.
3a a
.i
... w c;ll COtr1liCa d_2'/_!.lCC d C3 8.E.* al T-'i AG C2d N L'1 N ~~ ! O.I C 5 '~
2 i
_ _. _.. a t,. '1 %,
n
- n 1
- 7., 1 u.n,
s a i v.i
(.,
i e
4-
. o, o.s,,...cA :i _ A J ]. 2. '.,..a. i nr...2___ _ _ _ _ _(' en, - 4,4
.~.:
s v o n i u,..~1,.-
_s..-.-
2 J.2 0,
i i
~.
m f.
3 F
_ _ _ _. _ _.. '1 i a t. ~'.' a" 3y'.'..'"..'".2.. _ _ _....... _'.2. 'y'F;' 3..'1C ' . '. . _._. m'
.~.' H. i s.1 (' '. t.i ~.
I.'.
i.b..: C'.4~~
M ' '.- P v
o
- c...,. s i m. a~ eq si
.. i i..i.q. +._
- u..
c, p. a
- 7..,m;2 1, m_,,.
1,.
t, a..-.,. a..q i.. 1..,, c.,.,,
g 3 i u,.,
- n., i.. _.,,
~.~. a. __g..,..q 3.s-s__.._.._3. _... _. _.
. i
. v., 2 v
--u..-
t,.,,4 4.,.,,'
LJ g-3_.- 2 o o u. e. 6.,._ -_s. _.- g 'l_n.s_3
..l a,.-_ _ _
_..__o Iu._.
2_.
a,,, ;
. n.,
c,. 'l..,. f,..,..
c.
...--__,..g-,
.,..r 2.:
- c. 2 L.
2 i s
... i4 n / r'. -- oo n..r.,.a,ml 1 i ; i :;...s.e,_.. _, _. _. _.. _.. _ _. _ _ _ _ _ _. _ _ _.
m.
~.
,,..c
...s. a. -.,....q..
- r. :.4 b c...*.- - - -?...., 2v...y. - t. i-u...._.___t a '. n...._%.,,.t a. a a m
.o 3 -
.,.C,,- LO ],a*
g,,1
- c
.,4?.
4,,.,
3..,,..3.
--.2 C.M.i.o.r l..s.e._n. :
..u.
-m. _.e. ;... i '.. a-.
. )i a.
vi i.
. _.. _.. _.(.,3.p l,. c.v.L;. _., _ _.._ _, _.r...u
. u. ; ;. -.,..
3 1..,i 3.,,,.,.,,..r.
. _ I w,,.
,.,3.,.,,_
.,73. s a-_i.sq,a..u, g.,...,,.2._.3., n_.i, a..u i.R..,
,____.__.._a..
3., t; u
u-y, I,. c., (, i !.,. S. _,_6.-
.._T.,...,.,_;. 6.
..._a i_I_L C _s.~. a _..
-~. *.u e"-, t - '.r " - -
- r.. r-,
e [s,,.
,s,.
.-. r.. g_
- r.. I nm 6 l;._
t.
~~...t
.._3 r'.
,nf.en,t<.,,,.n...o. n. c,
.e_ n..,s]
r_ s. <. a~.*.s...u,. pi
,,a..1..
n a a (. s,
3
.. ~
u.
c, m w.
. t. a. g g..
- .~ - ~
ii
.a
. e..i L
8
- 7.,. 2
.~.
,f n., 2 5 c,. i.. '..%..- -a a_
u,..-a
".t 2.]
r L, g 'i a,
- n. '62. f a. t ' n c3 '- p.
- s. t c.. s e.
L3,.
- a.. r,. -..%.
..a.. s..
1 m.
~
--a
~r
,e
- ..a
(,..:.. w.
- 4. ;i a t..1.-
1 :.
- p. t,0 U. p. J... 9:i L.% a_
. y T. 'I
- .~,,,.,,. p,- -
Q z.;..a h'i - '
r"-
( 'n i w
s -../,,.... a.. u a )
C n.1. f,, e,v. e G-.
W. 2 n!I.,,.., a r
..s. - u.4. :.2 u.,..J2 a
ia
,. * - :,. - :.. z. ': c,., }
- a. :..~
,a t=..
p (; n 'i a f _ c ; : : e... u. 's
(,. z...,ci
.,,e
- o.... c.. ~, i-.
.-.e.,-
e,. -. -
3 -.
s-=
.v.
p v.,
i.-
.ii
_v-J.- k'., O* ~ 1 p '/.a.-b
- c. n. a 1..~.-
' "' n 3 - /. q ;, ^ \\
c.
., /
- 3. f.
- t.. i
', '1 1 I _32.
T
-, s,. i. 8 (,-
...g 46-w
.4 f3
(
w
.. ;..h.
i a". 8
-.u A t f4 v) j8
'..S.
c 3"N,. a 6 LI'I ct.,
.4 g
e, g
- pl%
L.... J. i t',. -
ei..
_a..I.
a.L.
. 6
.~,s..M
.L.' c..,. u,.r ~, "..e.,.
- n..: 't.s L-w,, e ".. a-i.c L3 :i
.r1.1. m -,, < r :.,. il t a.
u..
2.-, 'u
~ :,
.s.
v.,,;.
. ea_
=O
=
e
_ r. _ -.n.
~.. '.
-.--_......'.2.4
'1 '~l' ' r..
i"....:
M..,
u....-a.-,
-.i
..i r 3
.., -... i/ a_
v
~...
- 2
.--O,[]%,
'2
.=-
{,
L.
g
- .J 19
_.i ]
T j
f '*
I
- I.
+
I..gul l t,, L 6
U <(. I m - D.p: nn u./ d, O r.
t, r T g" a
,m..
c
. t t.
e... c. cm a NUCLEAP REGULATORY COMMISSION EEFORE THE ATOMIC SAFETY AND LICINSING BOARD AFFIDAVIT OF GREGORY C. MINOR On Behalf of Inc.ervenors Mr. & Mrs. Alfred Coleman Regarding CONTENTIONS 2, 6, 9 and 13 In the Matter of PUBLIC SERVICE ELECTRIC AND GAS COMPANY, et. al.
Salem Nuclear Generating Station Unit No. 1 Proposed Amendments to Increase Spent Fuel Storage Capacity Docket No.
50-272 March 26, 1979 I.
INTRODUCTION My name is Gregory C. Minor.
I an a partner in MHB Technical Associates, a consulting firm located in Palo Alto, California.
My educational background is in electrical engi-neering (D.S.,
University of California at Serhelay, 1960, M.S.,
Scanford University, 1956)
In -addition, I participated in Genotal Electric's 3-year Acvanced Course in Engineering,
- r;1 h c i a; in 1963.
A full deso-i?uon o f my e:: peri;nce an i sach round is attached at the end of this affidavit.
3 During the perioc betraen 1960 and 1976 I was employed ay General Electric Company in engineering and menagement posi-tions involving the design of components and systems for use on nuclear reactors.
These systems included reactor monitoring, control, and safety systems.
Between 1972 and 1976, I was Manager of Advanced Control and Instrumentation Engineering; responsible for designs of new safety and control systems whose first application will be on BWR-6 plants.
I am presently a consulting engineer uith MHB Technical Associates, consulting on nuclear power issues for public and private organizations at a state, national, and in ternational level.
I am also a member of the Muclear Power Plant Standards Committee for the Instrument Society of America.
II.
STATEMENT AND DISCUSSION REG.iRDIMC INTER'/CNO2' S CONTESTIONS 2 AND 6 The following is a statement of the Coleman's Contentions 2 and 6.
Because they are treated together in the Motion for Summary Disposition, se will also treat them together.
2.
The licensee has given inadequate consideration to the occurrence of accidental criticality due to the increased darsity of compactica of the spent fuel assemblies.
Addi-tional consideration of criticality is required due to the fo l lowing :
A.
deterioration of the neutron absorbtion mcterial providad by the Boral plates located between the spent fuel bundles; B.
deterioration of the rack structure leading to failure of the rack and consequent dislodging of spent fuel bundles 6.
The licensee has given inadequate consideration to qualification and testing of Boral material in the environment of protracted association with spent nuclear fuel, in order to validate its continued properties for reactivity control and integrity.
There are a number of issues of material fact which apply to these contentions and which are not adequately addressed in the Applicant's documentation.
A.
While there is experience with the materials of the proposed high density storage racks for Salem, signifi-cant uncertainty exists as to the corrosion effect and associated life of the storage racks, including the stainless steel and Boral material.
B.
There has been degradation of the Boral/ stainless steel racks installed at Monticello and Connecticut Yankee reactors.
The Applicant claims these problems have" limited relevance to the issues in the proceding" (Liden at paragraph 12)
However, there is no evidence presented that assures these same or similar problems will nct occur in the proposed racks for Salem..
C.
Very little in-servien experience is available in storage pool rachs with vented cells, as cell venting was not anticipated until leakage and associated suelling recently required nodification at the Monticello plant.
D.
The expedient of venting as a way to deal with the leakage problem is a major cause of much of the con-cern over the rack material performance questioned in this contention.
The basic design and materials evaluation leading up to this specific design intended utilization of leak tight, encapsulated Boral.
(Liden at paragraph 6).
However, the Applicant has discussed venting at some length.
(Applicant's Motion at 7, 8, and Liden at paragraph 8).
There does not appear to be sufficient analysis by the Applicaat of the opera-tion and effectiveness of the rachs in the event the cells require venting.
E.
The September, 1977 reporr by Battelle Mor'thwest's A.B. Johnson, Jr.,
" Behavior of Spent Nuclear Fuel in Water Pool S torage',' D:!WL-2256, subs tantiates that the Boral cell venting decision may have significant corrosion consequences.
To quote from page 36 of this report-
"In most cases, pool and fuel bundle materials hav, appeared to function satisfactorily in boric acid fuel pool chamistry, but fery fev detailed analyses of the caterials are avaitable.
alv + "
corrosier behacior has been subs _na; cd n
in some borated pools.---Considerable aluninum corrosion also occurred in crevices on the canisters, perhaps due to oxygen concantration cells."
(emphasis added)
This experience seams clearly to indicate the possibility of corrosion problems with the design as currently antici-pated and is certainly an issue of material fact.
F.
The NRC in their SER cn Salem make the following obser-vation regarding swelling and venting.
"Upon exposure of the Boral plates (B C/Al Matrix) 4 to the spent fuel pool uater, galvaalc coupling between the aluminum-Boral liner, alu:ainum binder and the stainless steel shroud could occur.....the hydrogen produced by corrosion of the aluminun will be released by venting to ninimize bulging."
(SER at 2-15).
In this instance, it appears the NRC analysis assumes the cells are already vented which is contradictory to the Applicant's assumotion (Liden at paragrnph 9).
G.
Based on the above, there are sufficient issues of material fact regarding the possible degradation of the rack macerial to require that these contentions be considered in the hearing process.
_5_
- III, STATE:IEET add DISCUSSION REGARDISC IUTER /EMOR' S CD:!TESTION 9 The following is a statenent of the Colermn Contention 9:
The Licensee has given inadequate consideration to alternatives to the proposed action.
In particular, the Licensee has not adequately evaluated alternatives associated uith the Nuclear Regulatory Commission adopting the
'no action' alternative for licensee's application, which would implicate the following:
A.
expansion of spent fuel storage capacity at reprocessing plants; B.
licensing of independent spent fuel storage installations; C.
storage of spent fuel from Salem No. 1 at the storage pools of other reactors; D.
ordering the generation of spent fuel to be stopped or restricted (leading to the slou-down or ter-mination of nuclear power production until ultimate disposition can be effectuated).
The following are issues of material fact which pertain to the above contention:
A.
The Morris Operation has applied for an amendmant of their license uhich would expand their storage facility to 1800 MTEM.
However, the NRC i. their review of the Applicant's alternatives only considers the exis ting 750 : TIDI capacity of M.O.
Although they acknowlenge that hearings for the 1100 MTHM additica are temporarily nalted, they could resume h2arings at at anytime the M.O. owner (Ells at 14) decides to do so.
B.
The MRC mentions several alternatives uhich'could be available in time to take fuel from the Salem site if a nominal amount of transhipment is employed (EIA at 14, 15, and 16).
These possibilities do not appear to have been adequately considered by the Applicant.
C.
These facts should be explored in hearings on this contention.
IV.
STATFj!ENT AND DISCUSSION REGARDING INTERVENOR'S CONTENTION 13 The following is a statement of the Coleman Contention 13:
The Licensee has failed to give adequate con-sideration to the cumulative impacts of expanding spent fuel' storage at Salem Nuclear Generating Station. Unit 1 in association with the recently filed propcsed amendment to the' application for an operating license at the sister unit, Salem Unit 2.
(See Amendment No. 42, Docket No. 50-311, filed April 12, 1978 uhich p roposes modifications of spent fuel storage uhich the incervenor believes are similar in scope to the Salem Unit 1 application.)
For example, the Licensee assumes an increase in releases of Kr-85 by a factor of 4.5--due to the factor of 4.5 increase in spent fuel (Licensee's application, at 10).
A similar increase, absent exceptional controls, can be expected at Salem No. 2, resulting in a cumulative increase in Kr-35 emissions by a factor of 9--almost a full order of magnitude ihcrease.
(If similar spent fuel increases are postulated for the cem.panion unitc, Hope Creek 1 and 2, nou under construction, the cumulative increase could rise 'ay a factor or 13, or almost tuo full orders of magnitude.
The following are issues of material fact related to this c on t en t ion that should be reviewed in a hearin; process:
A.
The Kr-85 releases discussed in the SER and Applicant's Motion appear to be normal leakage values and do not cover the magnitude of release cue to an accident in the pool (such as a cash drop accidtnt) when there is more than four times the amount of fuel stored.
The NRC includes an arbitrary 114 ci/yr release but does not cuantify that in terms of an accident or deterioration of the fuel.
(EIA at 7)
B.
Applicant's Motion for Summary Disposition states that Zircalloy clad fuel has been stored in U.S. reactors spent fuel pools for up to 18 years (Liden at 3).
This is only margiaally true.
As reported in the Johnson report (BNWL-2256, Sep. 1977, page 14), only one circalloy fuel bundle of pressurized water reactor P
design has been stored in a pool since 1959, and that one is not at a commercial reactor site.
Johnson's report also states (on page 3) that " detailed, systenatic examinations of fuel bundle materials have not been conducted specifically to define storage beb tvior, because of the expectation that the fuel would be reprocessed after relatively short cool resi-dei, c 2. "
Johnson recommends that additional investigatior
-S-
be performed, "particularly if the stored fuel inventory is expected to move into the twenty to one hundred yccr time fraae."
The pacential impacc of longer term storage cn radiolog' al releases should be evaluated and discussed by the Applicant.
C.
The URC states that there is a generic review of load handling operations in the vicinity of spent fuel pools to determine the likelihood of a heavy load inpacting fuel in the pool. and. the radiological consequences of such an impact (SER at 2-6).
This should be evaluated for Salem as it may represene a r.uch greater release than discussed by the Applicant or the NRC.
D.
The Applicant and the NRC take credit for four years of discharges of reactor fuel (see for enanple, EIA at
- 6) but the Applicant admits that raintaining Full Load Discharge ca si'y "is prudent from en operational stand-point."f-Su:h a capacity may also be nucessary for safety rensans if maj or core internals or vessel leakage rec aires rapid repair to reduce radiological releases to the environment.
Therefore, the Applicant's analysis s'iould consi. der maintaining Full Load Discharge capability and there y the incremental storage in the h
new rachs is one year old fuel, not four years old.
(Ltden at 25)
_9_
5 The Morric Opcration Consolida 2d afety Analysis Report (CSAR) reports an cY.perience of radioactivity release from spent fuel at the Morris Operation in 1975 which caused the radiocesium reading to reach 30 times the maximum permissible concentration in water, !!PCw (occupational).
(CSAR 7-8).
This appears to contradict the NRC statement that "there has not been any significant leahage of fission products from roent light water reactor fuel stored in the Morris Operation (MO)" (SER at 6).
The possibility of such a leahnge and possible release to the environment should be evaluated for Salem.
F.
The Applicant has not specified any in-service inspec-tion requirements to verify on-going acceptable performance of spent fuel :naterials and possible lea'xage/
degradation.
G.
The Applicant has not indicated any contingency plan for emptying the pool in case of serious degradation or pool leakabe.
H.
Based on the above issues of material fact, the Inter-venor's Contention 13 should be addressed in the normal hearing process, V.
CE-:CI,USIO:!
Basec on th.: issues raised in Sections II, EII, and IV of this afficavit, there are material facts regarding Intervanor's (Coleman'a) Contentions 2, 6, 9 cad 13 which need to be resolved in the license amendment hearings for Salem 1 reracking.
)+ -A q cmy b) b GPlGORY C. 'IINOR Suhacri. bed and sworn to before me this day of 1979
/
"otory Public connission expires
..7-r-.".:_-,
--.--.-r 7 s-~_;;,
.. ! rL ; $L f.
M
....... f.,... l a. 4 f
3
> 3:-
-'~a a
I ;- *1
_ F c ;;
(,
c'
..,. ~ ' ' r 3. r
?
1 r*
e
, ',I"'.
n : D,a. ".a
<- ~-
.a C.N J 3 ?".' C. Minor
.u. - ',_.'- -. o, 4 m.,
,1 4.
.u..,. m, S t 4 r.,. /
,,,..a
.~
R a '. ;. 1 :0, CA 94305
(.,., 2 ) 3., 9, - 0,.,/,
4
- e. v.._n e.,.'. _r "4 p.r t
1976 - Present MH3 Technical Associates, Palo Alto, California.
Engi-neering and Energy consultant to numerous state, federal and private organ; cations.
n..aj or activities inclu,_e s tuales or sa:ety anc, ris,a invo, ve c, in energy generation, provicing tec3nica,n con-sulting and enpert witness to legislative, regulatory, public and private groups.
,ecent,.y completed co-editing a criticua c: ene n
?.eac tor Safe ty S tudy (WASH-1400) for the Union of Concerned Scientis ts and a major risk analysis for the Swedish Energy Coccission.
1972 - 1976 s.anager cdvancec Contro,. and Instrumentation sngt.ieering, Genera,-
i 3 e c tric Cocp any, a,,ucle ar c.,nergy Divtston, San Jose, Ca3..trornta.
c-
"anaged a design and development group of thirty en.::neers, cuo c;erical anc, two te c.u.nte tans in de s t en;n t-systecs Isr us2 in ene a
a i
measurecent, contro3 anu operation or nuclear reactors.
Invo,tvec a
o
,eu..# 'a _4 o.a,
-'a "- 'i u - 1.' ' -
co---..--
v,. r,* i r.". o th. a -. e a - t o - d ' o-4,on.
a4-, c
- n. egu,tatory Carmission and cus tocers, both overseas and doces tic.
Responsibilities included coordinating end managing the technical contro1 systems, sarety systems and new contro,. concepts,or use on
.ne nent generation at-reactors.
_ne position incAudec..eapca-
'bil.i
- v..fo-c.anda ds mppl i c'b'me ~ o a c a -
u^ 1-
- 4... a c. "_~_ u_ n _ '~ r_ i s..,
a d
',.e.
o m
um-oa o.=:,- --,a
_-, o c-o.
- e gc,o-s,n o ;. s yto r_
uu,_-
s o,.ac4 t,
-u
- u u - -
u
- ud o.-
m y
The disciplines involved included electrical and mechanical ensi-neering, seisnte design and process cocputer control /progr=--ing.
,an _.i c, / o m
na
- Ga..v> - 21 Tiacr 'u-C o r ";,
- u.,,.., c.> -.
o,ac.,
Con o1. Sy aas-
- s i,r..
o -
3-.
.~
-v
':2 clear Energy Division, San Jese, Calif o rnia.
_ -ud
..', la 3- -,x - = 1-ww, ;
,,2
,., t,3, 0.: S e t.e,u, e.,
4.., e o d.
o..a a.
.,, e.,
v 3v.
u3
.-..--u..
- 2... A.
-1
-d c
g--y 4
- e. k.. o. A3
.9 4
,A d a. i ~..
u,,. u, - a c-
.n.
4,,Lu v-
- L.. a-
.i
-.u a ~a s m L
- q. 4. 3~0 4-y u
3.., - 3. ; S.,.,...,.,.. C s'
" e - ' w. ".. "_,
o S u' # s, ",.
-.'.s'. ^~~Wo G.CV, 1
N
- s. v
- l 4
c v, o~ _ '. '... _','
o o "t
.--.o o
- o. ~, S n o., 3 t '3 ~1,'
-y] z,4 s. _3.4 C a o "- u# #.'. ' ~_4 ' ".. ". 4
..,1a--
- -,. o ~. '. 3 -
~ " -
,. 3 p
--w----
~ u;
-s m
a C c, _,. v. t a
L3
,e p.
4., e,. 4,,,L..
- t. e.,- -..
u
.,3 4,.,
3,,
_..,-..c~...,.
o y
u _ o.,, -..
-. a v
., n..
s. - - v...,a u..u R n_,3.l ~ t o "j o e "s"t'*.."..2'..
'a' T..'e l l u' a'
, ^ " a' o 7. ".. e.l,
a
9/0 1
.t'...,.,4... 3 r, G o_ e..s. ~' l " l e _ t - i c
~n. -.o. :1..,,
'i.w.l" F 1. c&:"
74.-,..
D# f o a..,
- ic a
('.., 1, J- - o. m.. a.,
~o ~ n
.,r.,,,uo_,
.u.
- t. a, yc,.n 21b 1 n--
& c,.- N.. _2 d_ueiem.. o#
4
.o oa
- o p ^- v.i.# #. '.' C C "u
. ^.I au d i n o ~u'~ '~' 2.9. "w ' " #L C "..
-- ^
3 fo, GCC a_a
,3aCLo.o.
I r,_3 e t 1
u c4o - gn
- m. _ s, C o + '-) J ? i._.,f uo,
,<....r..e 4n 2
..,.., L t.., m c
o, v
e a i.
oo
_..yo..., r_ n_
o.
o I n s t..._> r...'. ~.. ".1 uo u+-
uo ~... _' o' " _=
.._"._c,..t_"_.
1".. t.~. -
j
...:,c o- - cu
- 4...,
o, ~_ m,. u g o.
.n a m. e g -. a c-. r_ a p1,.,m_.
.p o.. r. =. o..._a s, s_ a g a
n u,
o o,, o t,_.. u e o~, a.. gue.
m _t o. 4,u u n _, d a_ s i m.,.. o #.
<2 a
e s,ro
^_a
- c
...' n". '..,~
- m. y _.
.oo w..- ~ ~.-uated'
- r. " ' a
- w. ~
v o. a. r o ~o.
o c..v -. c s a "-.. o ' - '. t. '_ o'
. H. e 7
included on-site check out and testing of a cocplac2 reacar control
- o. -.o. n -' '*. o_,. t ' -
cm,cuo
- 4. 1 " 1 ^_
o" i b.es -.
D.e c.i. za d
...,.-..I a '..
m'..
ou.
p c.en t for Nuclear Power '.bnitorin,- S,'rs tan.
1e, u.
'L, 0 )
ce s-
.p_..,7. c a d F,. c '. n_.2.. 4... a..D%'.,._,"...
Ga. n. a. ' l 71 e c -. i - C o u.o,,.~.,r,
- 2. a"o,:..... _ o-m g
m u
o In a no n.,.ng ton, Ca3trorn.a anc, Ar..cona.
,ota Ing assIgnnents in a variety ot. ciscip3a.nas<.
n Reactor maintenance and inscruceat design,
. engineer,.
4 rc anc D reac co ra, n..an;orm,,o.asnington.
Circu't cest;;
and equincent caintenance coordination.
t m' o
.'.1. m ^.,, C '.'- _'..# o....,.
Da. o-d o r. E n. d, ". e =.. -.'" c o.,a m,.
D 2p u
-'.sn. ', '.
u o
W o
'.s-v~1 da_ o' i c.'. o '.. v _ m_,
co ne l a..
o
.# o.
T. W. ~ s.
d a
y.
Dc' :'., i,e,.. rai,d, ~.. a_ - - Cm..e"
'r Da_r,'
~ ~_"..u,
- 3. "...~.'-.,
2.- 4. v-'".. a.
De o ' a..
o 3. c o *. e d ' vi..., c i... c".'. - -,.
Design Engineer - Aconic Pouer Ecuiament Department, San Jose, California.
Circuit desien and analysis.
o H u
.m... - - ?o _e'. "..'.,
0.a,. 0 n. - _. -
Sf-_a_
S ".o-r_m' ~.o~ n'..m,......,
O Du's 4 01 c-portion of sate 33-ite propesal.
repare contro3 Ca3.-.1 o-n;a.
r p_ e u,1.4,., u 1 s c :3 c c - n.x, 4 a.l.
'". 1 4 "u c' "j o. l.'..".. &n. c, C ' >. m... c. 4 c..'..
t.
-u..
w
+
el e
( ~.T ' ~> 0 ),
San a
"'v.b..a, C 1.'.'. & o.. i '
.orn o, a
- e.... u - y s 4 o-u, _
D missile enchan>es.
a
- e. a. p g, - u _s.., S $---
'l S C *.,a 4 m.
, g y w-P, ;. ** 4 m... *- b.. i. g n a v= 4 g o C....f. 3
,3 C a
7
.u-w.
7 j
2-o
,J c,..a.,< uu C, 4
- a..,., 4. 3 a,. e., e.,
- -.. u 3, 1 o.,
1
., 4., 4 4
.3 c., C, :u-..,n..
e,
- 3..s.
3 n.. o..
u-f.,. -
-u 3_
4...
..,'...,.4,,.
., o J a.,D 1. _..
c,.t au r.. j o. o<,
.n a s,.,
Cn.,ia
,C C u,.,.,, S 7.
1
'4-
.,,..-4 a
j
., u v o.
f.
L r ca- -. n_ C +,. 4 m, _
- o. m g e r.. _.,..: c.,.., W n u,.
. _3.. 3.,.. _
-. s.:. 4.-,. a~
.O..,.,.,.
. s.., a_,
h..u,c,e,
?3,..
3.-
v_--.
., 4 -
.7. e. 4a. d L, o v u w.r,., 4., q l.
o'.6-w-2
.3-J
- 2 o w....,.,
- a,
o
.t.u q
..,..~.
n.
.. ~
.. u..
... i y.., 4_.,-_r
- r, c,.1 4..c.,,o-.. -
,r_ Bo i.>1 e",
B C E -., I r, a~ 0.
.'renced Course in Engineering year Curriculum, Genar:1 Electric c v,...,,.,,7,
7_ ya s,
.e-..,
S tan ord Uni tersity, M5EE, 1966.
s g ('. s e r m m s. n' n.J00 s
.emy Care.i s e co m y
.$. i t./
I. n a d. J
.tt Tau Ba ta Pi Encineerine Ec torar"J Society o
a Co-holder of U.S.
Patent No. 3,565,760, " Nuclear Reacecr Po 7er Monitoring System", February 1971.
Mombar-2_m_ erican Association for Advancement of Science.
',J.., m_'D 2 *. 'J.J C1.3 a-p or,o.
.D l c.2... ~u g t,.n.,4,* 4.o C o.....i, L n 2_
Te.Se 2.,.
6 -.
-s boC2.0t'/ O2.
nZ'e ri ca.
s 9 ',9 "i p,s., f.4 y D n f9.s S
4r
.i w
- , o rn ;.Iune /, 1967 D
.3 4
en_4ld c,
...._-_4. u, u, r, - n_._,
~ ' u> _<.,e b.. r.<16.-
5 ' <3. ",
'ibs.
..n e a.3 tn:
..:..:e, la n t t
y,.).
,p.,.,,,..e,w. us 3 p..y
....n..o
..:. a t t...,..
c~.
1.
Testicony by G.C.
- Minor, D.G.
Bricenbaugh, and R.B.
Hub'c ard c -
ac to re ene.. comic varetv anc, icensin~,acar,,
, a. / o,
c_ e o..
43, t
r..., n_
._-.., v o.c r u..n Blac,..
o.,..,,,,ca._
p,,.,.. _ S c._,o.. c_,.,,_
..m,_
c.....
u
_v.
.. o._ _ m tion Fernit hearings, Tulsa, Oklahoma.
2.
Presentation by G.C. Minor before the Federal Minis try for Research and Technology (BMFT), Meeting on Reactor Saf aty
, m_ s o.n.,_..,
.e.<,,../y..te..m:s.a_
Ir.*a_f_aca i. ". " c ' a_.n. o n =... c_ o. o,.. " " " s._
.s m..,
31 and Septecoer 1,
19/o, Bonn Germany.
C.,yinor berore t.ne Call:ornia 7 egis 3_atura a.
testitony by G.
c.
m Assembly Committee en Resources, Land Use and Energy, A3 3103, April 26, 1978, Sacramento, California.
i, Testinony G.
C. Minor before '.s'isconsin Public Service Coc=.ss en, recruary 13, 19/o, suoject:
7_oss o: Cco3 ant Accidents:
Their Probacility and Consecuenca.
-Swadish Reactor Safe ty S tudy:
BarseoHek Risk Assasscant, HSB Technical Associates, January lyid.
(?uctioned av Swedish Deoartment of Industry as Document Ds1 1978:1)
L 6.
Th.e Risks of Nuclear Power Reactors :
A Revieu c f the '.72C Ra ac tor
,-daretv 3cuav WSn-1200 Gui.E G-l a / 0 uo, n. 2.e ncall, e: cf, ac. cc
~oy G.
C.
dinor anc R.
3.
Hubbarc ror the Union of Concerned Scientists, August 1977.
7.
Testi=cny of G.
C.
Minor before the Cluff Lak' Board of Incuiry, Regina, Saskatchawan, C anada, September 21, 1977 3.
Testicony of G.
C. Minor regarding the Grafanrnein feld Nuclear Plant, March 16-17, 1977, Wurnburg, Gernany.
C.
Testimony of G.
G. Senor and R.
B. Hubbard befora California S tate Sanate Cornittee on Public Utilities, Transit, and Enargy March 23, 1976.
13.
Testimony of D. G. Bridenbaugh, R.
B. Hubbard, G.
C. Minor to the California State Assembly Comnittee on Resources, Land Use, and Energy, March 3, 1976.
- m. a s i.,c e.;
ou D. G.
B 4 do..b n te.n..,
- o... B.
"a t'.'a o m-d, G.
C.
'.'#. ~z..,.
w'=.'.'."_..
r i,
w aa.= ;o - _ _. _
~ q
- u..a e a i... c o
.,., o n.x ~ _: c
=._n,_ m,,,,
.,., a _.. 3 o u
.- u 1976, and published by Union of Concerned Scientists, Ccndrid3a.
v.a a.
d t u..
S,. t u.
o
_d-
7.
3,
.,,,,.,.m.,
_ --rs.n...N...s..
U
,2
....3, a
- )
F.>. C. '."..n
, '..T. G. '"-
".',i. I.". r.~o.- " "u, a. r,. ~. o ' o.sc v a - 3vaun.m
- . C.
~
v-sv.
"w "u0-1 0o'5 8 p "-.", a... n u' u,
. '. u..i,. ' o..>.
D. ' u'.. ",
.r
-u
- t... s.....M. a.. n '--
u Nucle ar Indus tries Fair an d Technical :.ee tingo, Octobar 1972, Basle, Suitterland.
13.
The above article was also published in the German Technical Fagazine, :IT, March 1973.
14.
G.
C. Minor, S.E. Moore, " Control Rod Signal Mul iple7.ing,"
IEEE Transactions on Nuclear Science, Vol. 24S-19, Februarf 1972.
6 6
s..
,i-f
\\.
'M #
Y Y
/
~
/J m.,..,~,
%v
~,
CH n c q z. p--7.,, W),*4 m
.\\
hb*
, a, re y-E,t'. 9
.,us a
r-.
n, md. 3I.iiy.,5 ty s.,,
i g[t,\\
g c'M a.
LM 2 0 %>3 d ts
~~f F1.:. i.g. t :. L"; r:
i..\\. s e n r _
... - - _..;e.,i,.,
v
-(
t.
.i.,m.
c d
'q' r' l.Q
\\'W
\\
- t i.
- m. o..w
)
)
.c. [.,.. o. [ b, y,. b.. -.O
)
nJ C.~0 t '. J. %n.,. e,.
J 1
.,b.c.; Law.,(.
.L.
L ~. *, l.
.. :'. 2., e t a l.,
)
(Pronowd Issnance of !cendment
(
)
to Faci.j j ty Operatin; Licence
.tj en '.'uc le t: Gen.;:.:t i n", S ta t i on,
)
No. CPR-70)
Unit 1)
)
G RTIFl(Wil: OF SERVIE h r br cet ti fv that copies of M na.
utd St'pporting Mfidavit in 0;'; a.;i tion to th-L icense.;',.' b ti on fo r Sic' ut:. Di:>poAi tion, in the above-cantic: 1 omceeding h tve been ser ed on t.he falicwing by depr,it in the Untted State:.
ill, i i ts t class, this 29 th O.y of March,1979.
c e
., s
3 ' U -..
l~
C " f ' "' ' 'l [ n;.' U
- h, Loard Cur; i.. ". i 'JC > l l i 3 ' h' 9 '- '
3 y,3,t,'uctenr P.gu b. tory Q m.
mM e " c c'...'> """
C h 2 i rm -' ",
c' t'n ' 2 20- -m
..t Licerc.':,
.o: -
,,, o, ; p ' t o a ' 11. C.
r
~~
CNE 131'; J
~ e r # '
J a d i r.., n, * '. '. 2 0 3 5 L n 53t g, conne.r, Jc., Esq.
, 0..,,">
Suite r'u,-,.4,,,-;, fecc., h.......i
'u:'~'--
iiai C
' L 'h L 3 0 '
Mr Les ter KornSlith, Jr.
er.ic r,.\\teni c Sa fe ty and I
'b-
" l '-
E :r-U.S. Nuclear R;e.ulator,e Comissica
.is s.
n.=:u
- c I.uf.al f.icensin.,' Board n'.
.c,
.~c a-
~
m.atatory ca.xreccion 3.'.'a s h [ TH. '. t o n, DC. 20553 i ~
....,.,i u.,,
w.,
m.
D. C. 2 ',.1 ) ) '.'
.1:. ~ -
g.-
s,. c ' -.
- t..
-t
- .v...
n
.s 5,
'*)..-' [ /* b 2 [ c ' I *..-. 1 1 : c g.,
[., ' d
'?'^l e.
,e,,s.
'. ). l '. ',' A. 7 7.o I s ** b
- g
.1
.)
' - - h C.' .31 -
v.
.w T.
..,1 t
j,,
e de. -*.,-
-w,'we==.=
4\\.L 6**'"4 n.
j',. ; }_
, i r-u sw
- 1
- O' s
~
c . L-.,j t
T,'. G..
.s Q',,
j, r t -
1.,,,
y
.s
'L
(-
-s--
- 1. v,,w w k,
--, j i,.;....m i -
..w a
(' g 1
}
s 5
, i
e e
p.
(.
t, i
.,s
.u-d J-e.
c,, 3 al
...O
.F e -
.,,1 s.
)
-s - a e.
t, Y.......7
..w
.. } _
6.-..g s
v.!,_3.,,, s.,7 g v;,? ? 5
.u,
.. -.. _a. u. S' c. -. ;,
3 r> '.=.u 5 :c t.
S:c"er v>a.
0; ir
_...'s. r.5 ug a
-i c e;: to a,
.e-
., _ r c e n,.3_3 c : e ;,.. r,t
- b. nor
- i.
- Technical Associates E ic h a cd.'~ r yl i.n;, Jr., E L'i 3i5 California Avenue, Cuita 6 As is ta
- : G e r.e r.,1 S,lic i to r 1 c. t o
.0, Califoce.;a 952j$
n.. n 3
,,t.
.c - -,.
, ri i-
. w_
- u... c.. <
Cas Co..a -
e n r,....
Os.
f..',_L
'.s.t j j u^.".
% ' *,..3
. '. ' : i r '., '.- :r Je rse; C?10i C 2 '.% c L th:'.GC Stu EE L S.','u: J e.t r R;,.mai to ry <c..
u....,..
h,,3 'c.,"., ',..,,O E E E Ii'0C'_ _
LO W. Dir.
El'.anor G. Co}ecan
"^
- Eld
<. l f r e ' C. Colm:n 2"-'
g'-. 3g533 3 's "R" Drive Pe n n;,v ill, ':': k rsq 03070 n...
v ;;ce c;- :.: ' a 2; reta ry c
D a A : t i n.'..'. : S-r. tec Sac t i.on L'. S. ::n : 1 : a c P 2,.:12 to r,'.
Cori t u a. o n
!?a shian t on, D.C.
20555 r '
a
. /x- ).,/o
/
,/
r i
EITil: A. Q\\$1'aPM, ESG!I:El E :_ -
At tomey for inteevenors
. ;-