ML17138B749

Informs That Action on Encl 801216 Application for SNM License Expected by Jan 1981.Submittal Supercedes 801016 Application

ML17138B749
Person / Time
Site:	Susquehanna
Issue date:	01/14/1981
From:	Laverty J NRC OFFICE OF THE EXECUTIVE LEGAL DIRECTOR (OELD)
To:	Bechhoefer C, Bright G, Paris O Atomic Safety and Licensing Board Panel
References
ISSUANCES-OL, NUDOCS 8101280628
Download: ML17138B749 (38)

Text

DISTR IBUTItJA:

Reg. Central LPDR Tourtellotte Chandler Laverty Cutchin Chron."

January 1+,

1981 Dr. Oscar H. Paris Administrative Judge Atomic Safety and Licensing Board U.S. Nuclear Regulatory Comission Washington, D.C.

20555 Char les Bechhoefer, Esq.,

Chairman Administrative Judge Atomic Safety and Licensing Board U.S. Nuclear Regulatory Commission Washington, D.C.

20555 Glenn 0. Bright Administrative Atomic Safety U.S. Nuclear R

Washington, D.

Judge'nd Licensing Board

(

egulatory Commission 8c h

C.

20555 26tg8] g In the I1atter of DIE, NUCI ~

PENNSYLVANIA POWER AND LIGHT COMPANY and EO//0/I1~+~~>Oay P

ALLEGHENY ELECTRIC COOPERATIVE', INC.

(Susquehanna Steam Electric Station, Units 1 and 2)

Docket Nos; 50-387 OL and 50-388 OL fO Gentlemen:

On December 16, 1980, PennsyIvania Power and Light Company (Applicant) submitted an application for a special nuclear material license for new fuel for use in conjunction with Susquehanna Steam Electric Station,. Units 1 and 2.

This application supercedes that which was filed on October 16, 1980.

Copies of the initial application are available at the Local Public Document,.

.Room at Ostetr1hout Free Library, Reference Department, 71 South Franklin Street, Wilkes-Barre, Pennsylvania 18703.

At this time, the license has not been issued.

It's my understanding th'at",

subject to making favorable findings on applicable requirements, the NRC

'--"---Staff will issue the requested

license, It is expected that action on the;

'application will be completed by the end of January 1981.

I A copy of this application is enclosed for your information.

t Sin erely, OFFICE)

SURNAME)

DATEP

-p io /Z e~<Z<

Enclosure:

As stated cc w/enclosure:

see next page oELp J'Layertp: cr I//$ /81 Jessica H. Laverty Counsel for NRC Staff

~ ~ ~ ~

0 ~ ~ ~ ~

~

NRC FORM 318 IIO/80)NRCM 0240 OFFICIAL RECORD COPY o USGPO'980 329 824

R It II, a

Ri li y I R Il

~Il I

I' I

Licensing Board CC:

Jay Silberg, Esq.

Bryan A. Snapp, Esq.

Dr. Judith H. Johnsrud Nr. Thomas M. Gerusky Ms. Colleen Marsh Mr. Thomas J. Halligan Susquehanna Environmental Advocates Mr. Robert fl. Gallo Robert H. Adler Richard S.

Salzman, Esq.

Dr. John H. Buck Mr. Thomas S.

Moore Atomic Safety and Licensing Board Atomic Safety and Licensing Appeal Board Secretary

. .:l

~.'". I 5 'L\\ ty and Safcguards

.l ory Cc;.;I!.i ssi.on

"'%5

~

~ 'C t~!Ci ~ I! C~

v,

),I I

t

~

~

I I I L"'

\\

Lr

!:C

~

I-'

~

'I

~

\\

I

' '"!A!.S LICliNS!; Al I'LTCA~(

'0 PILE S41-',"6,X ~~ '

~l

~

filed pursuant to Title 10 Co e of Fcde:al Re"ulations,

-: ': tioI! to 1'eceive, pos>>ess,

store, inspect, and; <<c::age

,;.r fuel bundle/as>>emblies.*

This application sup'rcceds s

-'..i on October 16, 1930 avd has been revised to address

"~ ! l'y your Norm Iiet 1acll, It is ec}uestcd tilat the Special

';::;'." -,"..t;vi;::.;: L:ccvse remain in effect until receipt of the Oper~ting L;

T'.'s

.";-. !ic" iL!! l>> ezcempt from licensing e

s per 10CFR 170.11(3).

A.-.'-"..'>>.io.s c;.:i.>>'nivg this application should be or!iarded to llr. Thorn, s E..:;:.:-'off, ("'.:)- ?1-5543 of th Nuclear Licensivg Group.

~.

J Q

'tion is submitted in s @port of the appl icati i~ l.

>>y'..':.-..'=.! P~;:er 5 Light Com>>any r'

vox 0

.;!: "n, ':.: h.

1S105 0

': SS OI..'.,i"',GE SITE P

o; -; 5!!>>ol!ehanna Stcam Electric Station (SSES) is located in

."" !..;:: To.-..-'.!P, Lu=.erne County, in east central Pennsylvania, about

,.!." m'.'..~

.'-beast of Ber>>icl;,

P nnsylvania.

Dg

.c "I

!Q fuel ma,l, tact !1 cr

!!!!dI c 4 1 th cha:lne l af. ized.

~ ~

F ENNSYLVANIA FO'Ve'.-R 8,

L! O'HI CO.ii?ANY

/iP) 7

J..'.

~

~.'

v.l '.eI si'rc:)

L)).u 'lji..a.

) ivj COua'4l.s I

,.;! (';;".);. in'icense, Docket No.

0-387 '.".d July 20, 1LiiB Lvj

~ -lc

.::: il))eh:)nna

.>team Elect).,ic Stat io; t')'it 1, is !)ereby inc-r

.::t il:.y r:f' e!)ce

~

Infor)))a tlon co))ce) fl ng cont"ol 'i)ld o):ne rship of:. he a!>plicant is also set fort'h in >!".

- @lie

! in for Cons) ). c:'.on

~";'m) t and Operating License.

'). 0 B.~.!'>IOAt",1'IVE HATF RIAL Initial Core L<<<-.l '. s=-::.'i,.s

.::.'.:..: scluare dimension of

".;-11 e/as s e:.;.b ly

5. ':7 'n.

.)el length 150 1)l.

L"".".'11 uel bundle/a ssembly.'i: ~< h 176. 16 in.

'I I I /

S

~

~

~

~

...1. '!

srjua re dimension of

nel 5.45 in.

1 '<<~ h-:nnel length

..:.el;;a 1 1 thicl,ne s s 165.91 in.

.OSO in.

ii.>(l i l 'xr t)~j)e S x 8 = 64 rods 62 fuel rods 2 L:ater rods l ':i"1 rod Pi tch i) <.1 ~cd clad thickness P<<d c];.d m terial F) e1 r<<d outside diameter V')~'1 pellet diameter

).i~llet material

.". -,)):;a\\ fuel stack density 0.640 in.

0.032 in.

Zi caloy

.')S3 in.

.483 in.

U02 10.32 gm/cma

':.'>'.,)1 n)".:.ber of fuel

.:::cmblies 764 (3 types)

I

.'!.!..'."ii:T) U-235 enrichment (veight g)

.~'";!..:;. U-235 enrichment (L'eight $)

3.00

."'i'..:).e U-235 en).chment (L'eight

~/o)

)

L r asser)bly t>pe

.711 I.76 4u,;her of asse )blies

". r type 92 240

':"I 0

w. -'<ht per:.::.':;bly (kg)

'":er

-"e UO s:eight per fuel rod (kg) 0.0 0.20 0.44 3 gl.

~ 3 T

U weight per asse'!bly (kg)

(lb)

!,8?.96 182.73 1.82.45

.'3 36

}02, 8>

~l ~2. 23

<lts'I!

<n an<]

! << a t}<<>n of <<ach ix";e " el rod i n the the

}!1! } \\'St ei roc t.sent can be fo d.'n iX! DC 21307}

".i.s

."!!titled "5'>>'R5 St" ndard Plant Fu:1 D< s ign Summary"

(" :

}:=~ s 6 6 8).

T.:- se fi,"-!!res are in '."'ed

".s propriet:.,

.d 4

~ 3' of the Sus<I ehanna SES

<<.: R.

0th "r f !

1

}.

~<<'r Abed 1n.ikD!'09 ~4P

~

)gy L5}

1.7 S(

-'<'! "!';='-".m a;<<.unt of special nuclear

!::a: er-',.1 as kilogr;*s;.f !'- ')5, s-:}ich -.'ay be possessed at any one time is 3,043 kilograms.

Ti:s

.~,}r, s..,its the '.nitial core and fifty addi".ional esse.-..blies per r;..r! >.'>,...'lt tx pe

~

': '". s!T <ON

.-'.ll 'nitial core fuel bundles are to be de'vered to the site in

.!cco-.'~!,'.nce.s'zth shipping procedur"s a!sd arr"<<ui"ants of h'-}:al Electric Con'pany.

The fuel bundles will be shipped by the fuel

}'!anufacturer as uthorized under

.'iRC Certificate of compliance

!.u:..ber U"A/4";86/Q(F) Revision 8.

Fuel s"ill normally be shipped to the site truck with

~ ma!<<imum of 16 s.ontainers

p. r truck and wo bui'}<!les per container.

6.0 STORAGE COADITIOYS

• "! e fuel bundle/assemblies vill be stored on the refueling f1 ~<.r of

..he

~ actor Building (see SSES Final Safety.analysis

Report, S.i:.on 9.1) in either the new fuel storage vault dry, in the spent fuel pool,

)r in their metal shipping containers on the refueling floor.

'. hen

he fuel bundle/assemblies are stored in the spent fuel pool, the pool may be dry, partially flooded, and/or completely flooded during residence in the storage rack.

The refueling floor is surround 'd by str>>ctural steel and metal siding and, therefore, it is considered unlikely that a fire will occur.

Hovever, the use of flammable materials on the refueling floor will be carefully controlled as an added malgin of safe'ty In addition the' ovement of the new fu 1 vault cover will be administrativel) co!!troll d by -ppro,- i pla}'.t procedures.

The refueling fl.oor is sho.n on SSES Final Sa ";ety Analysis Report (FSAR) Figures 1.2-23, 1.2-24, 1.2-25, a!'}d 9.1-168.

Preop rational testing, to the ext..nt necessary to prove t';at tbe fuel h.:ndling e<<equipment is functioning proper'y a'!d s saic to handle the

I i ~ (

~

~

p.e

.l. '1 ri t i>

si'3il al "r,

i

~

~

i<

iI i

'> <i<<>

~ S

~

i lpt

.sBd lnsp<'i t l rlr!

'i 1 s!'.,".;"ent.

Firnct i so be

>'.~ne in acro..!a

, arlce L)LoceduL'es

~

~

).l be ti st<

<3 to i:.<: 6/teflt fl 'c<:ss,.>.y

'0 of 1 erfoL">in> t..11. specific filnctioils i.or activities pr or to tl.e arrival of the onal checks 'f the fuel i!and liig equipment l;c'ith appro' plant operatirig arid

' "<trliction a!ld, pr<'<, '.Latio!Ml 'ti si i i'.g nct1vlt'}es may be I <1 l il i 'ile l

< l l

I I <t r

<l v l (e g rc a <

v L I i l1 L< O 1 6 )

< itLO! i..'.10.!:1!

< '!l,' lit, 3!stal<'..tie:1! i<!!Lle 'lie..l ls b~iiiP "z )

L.....i

~0 /

i.

L C.

<rI

.,7

'-". s i!'-t'l l. -'

i;"."'.ct,,nich..'n<"'::.l. th ci.>>.on of ',1 e

." of "<".tiv.itiis,

'l>~:Le <:ill !:e no 'iact on r<<e.::.fe receipt,

": '< n or ~. 'L.~

>1.!,

ri.> l.

Irl:i<-.<lit:.<n tl!e ie:por!sible

'>> >oL L>n ".'<lent dl!L'r::g fuel r<>co i pt, ~nd 3.:sp 'ction act1vities w11.1 i!" <<iit.': orii y to ti '.-,'rlate either or. both of fuel '<<ceipt and o!1 acti'i Lt1es c r the coi!struction

<..";d preoperat1onal test1ng

~ Ct: r< n

~

<d 3> ~< ~ <: 'i '!ri

.;.:":n 'as

- ;;ci.ii

'e

~it

r. the fu"1 car'ier v...icle arrives at t!.e pl'rlt "~te, lt::Vilbe ta!:en to a pladeter>ni:ied off load

<-.r':a

,!.. 'e t

1 e s!:i!pi!:" i.;.r.".! ners will be

.: oai.ed 'c.n the caLL i.r v.!!icle..'ll ooil'l iontainers 3'ill then be taken to the r!.:loading bay on t.lie

~ ound floor of the Reactor B<<ilding (L:f672).

The r:ret':!1 Lniier sh.'pping containers will be realoved flem ';i!

i;oo..n.",t. r.;u'.; )ing contair. rs.

T.l lietal conta neL's, holding tlie 'fuel lull!dies, will be lifted to the refueling floor of the Reactor Building, where they can be stored for an interim period of time.

'i'he metal coi:t:ainers will be ~lac d in a near Ltical position,, iid the liundles a!e t len 1 e Aoved from the colltairiers:

The fuel bundles may be placed in the new fuel

~::,~ection si.!i".d t.o be checked for itltegrity and ninabel ng) or pl.ced in an appropriate storage location for future insp ction.

Upon remo:al of the fiiel bundle from the shipping containers, the plastic bag will be r;aioved prior to inserting the fuel bundle

':ito tl'e storage r.l:!..

Tl;ere is, ro way water can be entrapped within the open lat t.ice structure of the fuel b!Lndle.

Ão cl.i.iiible miechar.is ll

<. xists with which to block the 3-inch diari, ter no:.'le on the bottu!n tie plate of the fuel asserably.

All f<lel receipt anil inspection activities w'll be <'o:!trclled by tne pplicable plocci\\ures which are reviei:ed and a.">>:oved by tlie Susquehanna SES Plar.t Cp..l:ations RL.'view Co,..mittee

(:iee Section 13.4 of the Susqucl!anna SES FSAR),

and approv 'd by ".<<e Si!>>erintendent of tl:e plant.

The ultimate r =i ousibility for

.! i!'3 3

'. s

~ $ !3 t!;I' 3 ~;I-L 3 lt'r 't. ~,, lt ~

(! (

!L oL rJ-aged or 3'!3 cce )>>~b e

~ '>>, l 3 ll( i! !!!st:)e rL"ti!1'iafd tO the 3!aanlffactura~r) paCk": j ng t;i.'i 1 be in ar COrdaf!Ce wi!.h DOT "nd 1(jCER71 re(!!irement" and

"=!3=:).",~.! s 1L he made via a

1 ic'os ed ca rrier.

6.2 5:.'>> iv:":.v.a]uati>> n

. i.

t":;>>'.ae/~ss:!blies cf iL ba

=.:>.eri in 'he new fuel

.;a...,.e

!,.i-';s in tife new iuol st-rragr t, in <<:.!3 density

, '.Ore "e racks::.n the.")~f.t "

'>. pool. f!nd/or in th.ir

"!!."',i'i~ ":>>'

(-':!t!Lnae! S..iO mOre t<<

i I aari 0 (3) La!el 5

'I,'. 1 1,)e Ol!tsL(ie c.'le, a. i, ~. 91<> ('2

i. i. e

~

f!32 i

~'a 1

';- '.'p'g cof!tai ners a!'.e

..>>..r'.bcd,

.".<<d ti a".ir storaige without a criticality warnino system i 3 3:d

! n aa'aa>>=i>>>>.'..

afoot ji5 to taE s

".'('ci.:!1 !!uclear

!'!teri a ls i',(('sc,';it.i i

! 097 (i)ted JL!ne 6 > 1978

~+!(!n fuel lunriles are

-'(;

>>i '.n ta,cir fi:etal shipping contaai!L=rsa tile co!)'ir>>>>'rs will

',"'>iik.da ~'ore than four (4) hi"-h.

The cl-oss-sr.ctional si"e

.if "nays vill only be limited by sp..c available on the

,oor.

"..3'>>i!!g c itaiflers containing fa el will not be st fred i l.,:r,"iten five (5) feet to any fuel handling equip!nent.

No 1<< ","!',.i"i()fl will occur between fuel s to red in the shipping con(ain:rs a<<>..-,',~r ded in a CO<<CL'ete flOOr Wi.th a mjf!i~:.'!m Of One (1) it. Of r acrete bet een storage arr ys.

5<> lity safety.

These

'o! '"

. re>>! "ir"ed ~hysicists or n<<clear er,~i'seers and have

!lad

>>'.r':::g in

"..'.:R systems and fuel.

In addition they will 'oe c r'ifiid as fi!el inspectors for Sus(i!:ehanna S~S a<<d will receive all 'h>> c]assroom training giv n to uel handling or inspe'ction The cri i ality control and fuel rack design criteria for the new f!:el stor.lge vault and the spent fuel storage pool is outlined as follows.

6.2.1 CL'itica~lit Control - New Fuel Storage Va>>lt Rack T.!e; CW f!!el StOrage V:ult iS deSigned tO Llai!3 ain ia!ff

<.>>35 (see FSAR Subsection 9.1.1.1.1.2)

.in dry co!adit ons and when flooded with fat".L. '3, t;.en 0.7,".nd 1.0 g/cc.

The new:.uel vault is cov",.d by leak proof

.".!>> tel, removable covers which are co!lta;(ail,!d by

> t>>lt;f'!ie n r'.!1<IitLOilS aao;.! '.

I "n I.'wo

( 2) 3 a'il'.t C.~'t fS will be off at a tine.

The n<<w fiel vault reve"s

{- '.-'.R Fight fe 9.l-la-

.tt'!Lnent 1) overlap the s'

.a e vault curb and h've a

pLotective lip that prov nts direct impingment upon t! e sealing point.

The modif ed I-beams that span the

~".>>lt also afe overja;!ped by ',he covers.

The bean:s act s "f.ins to diL-ct r! n-cif f.-m t,'.!e covers to the

}j

~ ! 'g floor

. eq I ! !g is

'! ov ada'-d bv

\\ a!e covels

!.est

.g L!Don t.le cha "nel.'.n'l

!m u ipc L suL

".c s ~,le sass of the covers, and th-close tolefances of CrnStfuCtion, Ltak>>

e!PS

~::,"1-g-ble.

T!:e calculations of 'Sf a! e,abased

!!pon '"" c'.

'.e':jc:!1 arf ngments of the fuel array and SL!bcriticali!y..

s not d pend upon the presen."e of neutron ab-o

'a'at.efials.

To r,eet the recIU fements of Gea.= '...".c..::;.>>

Cf'teflon 62, geometrically-safe configurat',~as a"i el stof>>d in the new fuel array are employed to as-,!re Lh.it. keff will not exceed 0.95 if fuel is s"o.. d

.'..! "'ae e:ry cvnd~tion or if the ab"..o..al condition OS f'oo.!:>>g quater with a dr nsL"y of 1 ~, cc) occuLs

~

In ':'I'y condition, Keff is L!aintained

<0.95 due to

.:Ocleration.

In the flooding a!d flooded rrnnit on, the geo!!etry of the fuel storage array assures th Keff will remain

< 0.95 due to ov-r-moderation.

>>o limitation is placed on

"'::.e size of the new fuel storage vault rack array fron a criticality standpo!int since all calculations are performed on the b~.is of an infinite array of a emblies.

The tacw Fu:.1 ;" '.,- e Vault will, therefore, accor;=.".Odate fuel frc;! a..!lti-unit facility with no safety implications.

i'all handling conditions remain thee same and there is.!o compronise of safety considerations.

keu Fuel Stere*e Vault Rack Dealt a)

The

'aew Fuel Storage Vault contains 23 sets of castings which may contain up to 10 fuel bundle/assemblies; therefore a maximum of 230 fuel bundle/assemblies nay be stcred in th fu 1 vault.

b)

There are three t'crs of castings which are positioned to fixed box beams.

This i!Olds '!!e fuel bundle/ass,.mblies in a vertical ;osition and supports the fuel at th lower and upper tie ulate

w). ~ h;s'Lld 1 t > Qna 1

).-,

>.:q !

s'ljt !,. "p <,,

gr"vity of the fu.l ass-:.:ably.

c)

The lo'-er <;:~ting s:.. ~",rts the:;i:'!t of "he "ucl 1 undle/~sr,; b~y a<<l "e'tricts

! '~ ':- ".1 r!ove.",~cnt; 'he c::>>ter -::i top ca. tii:.>;-estricts lateral move~,ont nn! y of the fuel )->>~die/assn:.!bly.

d)

The hew i'>>el Store~'e 'a"!lt Hac'""

<. e

-!":.'ie r '~-q a}ui'!inurn.

1ateric] s ':" ~d for i"'l~!ct 0 l i e specs f ~ ed,! n accord i'e wxth

!'!s 0'. ;8 specifications.

V~'.e:~,:terial choice is based cn a

(onside-ration of '".e: usceptibi.lity

~f var'...us a!etal combinations to '.lectroc";~e>>'ionic re':ci ion.

'.h -n co!!sring tl:e."!.."-ceptibilit'f;;: '.>1s "o

galvanic corrosion y

a u.,'in> B and s ta inless steel are relatively clo.,e to".= ther insofar

..s their coupled potential is concerned.

The use of stainless steel fasteners in alumi:n!m to avoid detrimental galvanic corrosion is a

rcco,".mended practice and has been "s d success:";oily for many years bv the aluminum i.-.dustry.

e)

The minir!um center-tc-center spaci~o for t h f!::1 bundle/assembly b

~".we n rows is 11.8!5 inches.

The minimum center-to-center spacing within the rows is 6.535 inches.

Fuel bundle/esse-,!bly placeme!:t between ro;:s is nvt possible.

f)

Lead-in and lead-o!>t of the casting provi d s

g!!idance of the fuel bundle/assembly d!!ring insertion or. withd:.awal.

g)

The rack is designed to withstand the impact force of ~!000 ftlbs while maintaining the sa.".e c.'.,'ign basis.

This impact force co>>ld be g";>>~":ated by the vertical free fall of a fuel assembly from the height of 5.3 feet.

h)

The rack is designed to withstand the pull-up force of ~!000 lbs.

a xd a horizontal force of '.000 lbs.

The racks are d signed with lead outs to prevent stic.;ing.

Ho'-e'r, in the event of a stuck fuel bundle/as mbly> the li ting " il

. ill yield at a >>ull up fierce less tl!an l500 cs.

i)

-The rack is design d to withstand hori.cmental combined loads up to..22,000 lbs, well in e:;cess of expected loads.

~

i) f,".u~

o 1 coed!".;

si~nii:icantly 1

~

~

)

cl:er h.n the a!1't)able si ess k)

The xack is '('s i '!>>ed to h a>>idle

<to!1 i r":!>>)!>>:ti6 0<4 Qmis~ !o(1 r>>>dioi cti"e fuel <<! v>>.:b I.ias.

Criticality Control - S'c>>.

"-e of.:

(~ Peel

'n itigh Bi::sity

.")

. ent.'uel:".ac!;s The des 1 gn 0f L.)e s:: ~nt::.el

1. 301 s tot'a~~e tha>>'eff.'ill r:.'..ain ~0.95 "or both no::.t abnor-:.'.al storage conditions.".ormal co:~di 4'heo a.'Ltc fll>>"1 is "dl v ) flc r ii!!g a!id flo>el fritm

'".e hoisting e,"

1:r4 t.'

o!>> s e;; i s t

'>>n

!t 1 y>>>>>>>>p i>>>>Q I

.:1ta1 t

l" 1 rst e"t.

To ensure that the General !.asign Criteria 62 is m'!:,

the follolv'in9 normal and abnorr~.al spent f~.'".1 stolag conditions vere ana" yoked.

a) normal positioning in the spent fuel sto.age

array, b) fuel stored in contxol rod racks, c)

Pool l"ater temperature ncreases to 212'F, d) normal storage array of ruptured fuel, e) abnormal p )sitioning in the sp nt fuel storage axray f) moving fuel bundle betveen l>>ork rack and storage

area, g) dropped fu;.1 bundle adjacent rack The criticality'afety analysis vas performed by Nuclear Assoc'iates International (VAI 78-75 daied 5 79).

This analysis shovs that under all postulated normal and abnormal conditions, Keff vill remain < 0.95.

A discussion of the analysis methodology and results folio>>s:

6.2.3.1 The Principal Analytical ifodel 8

>>1

spc'ut

'uel storage r;!ck desi

~ n;

.a

!:e CIEE"!".~l!-8/CONC- !.::"../PDg-7

~. Ii">'t;.:', el moc.el "s t..:e b..sic

.nginoev!:.g tool.

ClKET.'!l-B is the:.'

lattice aversion of.".'iI's

!"lf ETAll code ':hic!> is a..:odif'ed '.! sion of the or.igi!..al

< "OP.'.-".D code

':nd ':high: ses a

nodi fied EyDi/B II cross sect!on 'l!brary.

COBC-BL.OE go."ser. -2s t! e -~"ul'.,~'. t d! f..!-'!~n

! ueory cr~iss-s<<ct i.ns for: !<<. ii> <'.rol. ~!-de.

7!!0 ! Dg 7 pl. &pa'a"! i s tl!e !i'el, 1

.'.lloi:n i~v,.:

r rc

', 0 spatial diff llsio!I l 'ry code.

'ilve t'.'!.s~ort to di.fl':.sion 4;c...ry cv! v,: 'n 's ~::;.;r;.'ed usi,ng the ilonte f"rlo !.:o'!

1

~!.;.cv",rd 'n Section 6.2.3.2.

The reference case sto.a,";e rack c".11 is sho';n in Attachment 2.

A zero curx'c nt boundary condition is appli d to the four sides of this cell to proti!!ce an infinite array effect.

Th two d -.."nsional

?"{'.-7 "e; "nce case calculations;.re

".,:ade for fcur r..".>'tron energy gvoups, t-o nash intervals per 'u 1

pin, a flat U-235 =nrichment descvip".on and a zero axial buckling to sim~!late infi.!ite fuel length.

6.2.3.2 The Verification.'!odel The verification calculation employs the KENO-IV/A"!PXmodel.

The basic neutron cross section data cc.;:es from the master libr;.ry of r'QJPX -

a 123 gvoup GA.)-TJ(ERil09 neutron library prepared from ENDP/B version II data.

The NETA4'L module of tl e

.-'.".!PX program is used to pevform a Nord.'"eim int:egral treatm nt of the U-23S veson

!ces accounting for the self-shielding effect.

The !'orking library produced by the NITAVL/A!IPXnodule retains the 123 group energy structure and is used directly by !K'NO-IV.

In the KENO-IV calculation, each fuel and

!iater rod cell is represented discretely, as a box type.

T}.e array option of %NO-IV is pplied to arrange the box types into a

matrix repvesenting the fuel assembly.

Then a eater reflection region is added to the outside of this matrix fo1 lo!:ed by the aluminum canister, void and Boral slab

rt gr'ons to cr-."..'r storage rack ce11.

'lo sir;..!1::te Lh al.r sl)gei7!ent of a 1;! sse r>>!; her of st.fi s~ e cess k

units, and for a

.;a rs-"> c a'2..-'e: ',r "iiti:a axial direction, specul

r. reflective corer.ition is appl'.:d 'o all si:: side= if t! e reference case

s. ir~ge "ack cr:.[1 (See Atta clrment 2).

T!rf t'V..'sC-'lt'/f'i.'r'PX

. .el has b'n b".i'.,."

against.arl'er C..'L critical. x:it.'s

rre:.."rrr:ed by Dr. E.

Jo!!nsor!

a T.a t.;o

~e.'i1 cold f.ritical, and th'ore r.cn>>t exp'rime.>>'s co!>.'.uc".ed by '.R. J'i:..":n art t: sre Batt el le Fic..'s! thieves t:'. ".'L' o 'v (PXL-2438).

Tt:

~ 't.-r r suits, ~'.'.!...

average calculated I:eff t o be 1.001!0.0"r6.

6.2.3.3 Basic As~sum tions T.>e fol'o"ing assu:;!ptions 'ere ma'e n t".e analysis and ensure that the study r".".11>ass a

CO!!SO l.va tive c".pp O = Ch.

l.

A uniform 3.25 v/o distribution in an 8

x S bu:idle (t'hich is more reactive than a distributed enrichment with t'.e s;:"e overall avera=e t'eight percent).

2.

Fresh fuel, o burnable poi:son.

3.

Hinor struc"ural m"mbers replaced by r'a ter.

4.

1 resh.:;.ter a t 6S~F.

5.

1'uel ass mbli s are channeled and centered <'hin the storage cavity.

6.2.3.4 Effect on React~vi" of 'Jncertainties Hateria~l Pro art'es and Rack Geometry and Fuel Placement (a)

T~am er tare Effect Usir!g the no-..inal storage rack ceil g:".etry, the temperature of the fr!el and pool l:uter t:as varied.

Inter-,.; diate steps at 32 F, 95 F, 120'1, 150"F lSO F, 212 F ere studied.

T>>e results of the ansal>'s s

c!.o.;s 10

(b)

Void Ef.,ec t T!>>e effect of @oiling (a.-." u".r>in

> i;">>al voids inside and outsid

~>f the rack) is st:!died by varying the voids from G/ to 20"'t a tc>!>>peraturc of ".i2 ~F with t1'e i",:>"inal p<:o!l>>etry.

The: s'l ts in '

i 'o "'"';! i >>'. us deer" >so in r,.a:;.t'.vity for.>>is.'.:;".e of voids

~

(c)

Boral Vi ith

":,. duction The nominal wid"h of >>:;,e Bo:al s'.ab is 5.250".

The ch::

e in reactivity d.!= "o th.

-0.03 inch mi>",i.".u ~

tolerance on t!>>.-'s..".dth is 4K=0.001.

(d)

Channel Effect The rack must acco.;-::...odate both cha!.:e';.d

->>.d unchanneled fuel..

Studies reveal t:h. t the channeled fuel in the rack is more rc.ac'..: e than the unchanneled fuel.

Taking the conservative approach',

the study here involves channeled f>>>>el except in the accident conditio.. where >>nchanneled fuel is dropped.

The decrease in Dk f!om ch;>nneled to unchanneled fuel is 0.002 in the base case rack (See Attac1".,ent 2).

(*)

The criticality calculations described

.'n this report are based on the assumption

>;..at the core of the Boral slabs contains a

homogeneous mixture of fine B, C and alumina'm powder.

An adjustment must be made to t,.ke into account directly the self-shie'ding effect due to the random distribution of B~C grains of finite sizes in the m'xture.

Based on a homogen ous mixture, the neutron attenuation factor for a Boral s' of 80 mil thickness with 0.0232 g/cm B-l0 loadin~;ras calculated to be 0.969.

The vendor 3 ooks and Perkins has proposed the value 0.963 as the acceptance criterion for their me sured

~ t

~ 8.

Based o>n

>s>>1 s

a>.a

'i sos

>.>>e i>

~

'i

.,>>Ci.'etween an attenuation factor of 0. 969

':-. d 0.963 amo>i:its to aboiit 0.3% 'k <<or the Susquehanna Spent Fuel Pool.

The reacti.ity reserve of the ne" pool is more than 1%

below the 0.950 1'.;.it perm>itt:

3 by.'3C; !;:>ce Bol al sle bs r,:."et'~ the 0 o63 c r:.t>>.'I "> 11 have no

!'erse ef. ect on th Ly of L':

pool.

(f) g>n~ e

'> n Pi t> h (>liiljl:h Se"'$' t j V" n: ) )

The "cac.i ~ity ef

'.ct of

"."..'; l'l t.>',

'<<.'<<'hanges caused by struct>>ra1,

>"nb>.neat-t>a>

installatio>I, and s ismic c.o;>.,g conservativ ly detc lmined by the n'itch sensitivity study.

The

."a1 culat'".-",s "e:e carried out on a 0.125 i<<ch:;ncI

>~nt.

".he pitch reactivity coeffice:.At wris

(

t>'Im..> ed to be about +0. 7%.;kj0.125 inch:'

ch reduction in the range from 6.875 incn >>'tch to 6.375 inch pitch.

(g)

Off-Center Poei~tionin The reactivity effect of off-c nter positioning due to improper 1'>ad>ing cr sO:;e natural phenomenon was investigated.

The calculations show that the reactivity decreases so no adverse effect oc>-urs.

Pesults of the Ciiticality.;.-.alvsn s (a)

Diffusion Theor Results The results of the criticality analysis of the proposed storage rack for Susquehanna Spent 'Fuel are snr'rized below:

PDQ Results:

Keff Nominal Case Dimensional and Positional Tolerance, hK Boron width Effect,

~K Temperature Effect,

~ K Variation on Boral Accept.

0.893 0.014 0.001 0.004 0.003

]2

~ n t

V. 'd

'ye]J>> c I d j, cs s C

0

~ 915 (b)

C.r o ~,;-.:..>>t,s..

~;~e Calculational

".". as The I%NO-IV verification calculation for the nominal case yieI.ds a ):off;slue of 0.912'-0.004

~.'.th 95'., cn: ".. nce

'..-,. er"al r;..scs$

ts f my 0 o0!s to 0 o'~0

~",;~ s:

)

s ~,Pq]

deduced from."'..5i's "t"nt-',.-...r! jng cal."I tlons.

Comparing the u",.ner bo;sod 95'on;iP'.e

>ntt t'al

".c s~

1 t of t1 e

• '"0

>>31 a "f d tne

'I'ug runs,

a. d b" s:- I:n::,;.:.0 t

ae I

t M ~ ~

>oi'-'c"i"zzs.j.ng res>>1 s a;-.>,;.;: "

1 0.026 in

'K is applied to 'he;s.-!" st:t:d d Dg:.'- ff to;provide:he trans"~ort d'A'"~.'on theory correction.

(c)

Say.-,~gr of ?os>>its Iteff (tip) ad'us t "d (fross) (a) )

Tr.n port to diffusion theory correction (from (b) )

Final Keff Design Limit, I'eff Calculational ihrgin hK 0 ':l5 O.i ~G U. ;'1 0..s50 0 's09 The final Keff value (0.941) incli ~-:s all the design specification tole'-ances, rs-..del bias, and the 95% confidence interval fro.-.le I," ~0 cal c>>la t ons.

6.2.3.6 Abnormal Condi t ous (a)

Asseably

~Dro Acc'de..t No adverse reactivity effect is expec'..-d from dropping a fuel assembly on top of a:"s lly loaded storage rack during fuel handling because of the large water th ckn ss (". 10 inches) existing between the top of assemblies already inside the caviti: s and the dropped assembly resting on top r.f <<he rack.

~Ioreover, the b."sic calcul~tit

~ al model assn!res an infinite f>>el ler"-th in she axial direction.

13

~ ~

i~: 1('o

.n assr. b]y located in the ou.:..-'-St rov OC the sto1age

<1.

1 y vc1 e an:.'

's.:, i.

'. he 3:.-. e li'y (lrs'.,:p d

during handlin" is "ssumed Lo 1o(i~so parallel t'0 an aSSCmbly in an Outer C.)ViLy -ith no t oral slab sc-r (t r it ng the tvo as sea1bl i( s.

Tl<e din:.nsions (C the racl: 11niLs and the S1>ac).ng 1S L(ie "."."'..'s the 1'er11ce cs".Se) 33 (hough .e

.d fuel is ii 1channel ed to

s)1e to the r(

C 1 i

" 'e 1 'tt'n(

ry Co 1(.,':, t

'sed) cise at r(t'v

( s qel') I ed 1n l ref' fre('c)(,, '.

f, i'

'", h;i 1",...1'

)~lux

( ons t>An.

'"... -. l, < i i; r,i; '.it increase in r):.s. t:."'.i 1

='s Li.,"in "0.5,. 'i 'n a

4 x 4 array t'i eh 8 >11(hes of pppl c('i t'n the outer caviLy.

(b)

Intergersosl

!!o(sera tion l ater (ensities from.15 to.75 g-1/c; analyzed.

The

) s's;(1ial)t Keff's are:

-4 group PD(} -7 model s

fraction of full vater density lieff

.15

.25

.35

.50

.75 1.00

.5691

.6276

.6845

.7556

.8392

.8931

~- KENO IV Hodel

.15

~ 25 1.00

.5301+.00?3

.5958+.0029

.9124+.0043 These results i;1dicate that the lim-'ing moderation condition exists vhen "at ',r density is 1.0

1/cm3.

Therefore r;;-'t':., is not a significanL'roblem.

I~<i h ~Rensit~Ssnt Fi:.1 Rnc!

Desien 14

p<o1."i.r. t. ri >g;::"..:

".-.; t f'..!.

'>l e high !'-.i.s!.Ly spent i uc'1 1'ac';:s a; e of;: . c,d a

'~ i "ed a~U: i.!num cons! ri ct

~n

!.on< a-ning.;,.

tron-:-.'orbing r." diam of na t'u'al bol on c"'bi'.':,l'.<C) n an;.1 ",".inurn la.t H x core clad vith 3100 'eries alu.".;inurn.

'rhi:,.!.utrc!.".;'o.ber is !.rarketed under t!!e trade

.".ame of Boral.

T."e core has a thickness of 80 ri!ils and a mi!',m.m 3-10 d~ sity of 0.0232g/cm The Soral

'=- sealed !"ithin t, o

conieniric square c.l '."iii',! t:.Qes

~Ie!'..""!no fter ca'ii d "poison cans".

Each r..ck co!sists;" si: ';.sic "."

1) top grid cast!-.g 2) bottom grid c.sting 3) poison can assr.;blies 0) side plates 5) corner angle clips 6) adjustable foot asse'blies Ars The material dimensional ch racteristics of th

!;.ck are:

Boral slab a) sheath thickness b) sheath material c)

Core material BiC aluminum d)

B,,C a real density e)

M7o B in BgC f) a/o B-10 in B g) 8-10 a real density

(:125 x 5.25 x 152)in 0.0225 in Alusis'm 35%

65%

0. 185 g/orna 70-77%

19.75

+ 0.30'/,

0.0232 gm/cm~

Inner can a) each side b) thickness c) tlaterial 6.155 in. insi'e, sou re 0.125 in P.luminum Outer can a) each side b) thickness c) material 7.093 in.

o!! ~.'i'.~-,;cp:are 0.125 in.

A u'r!1 nuiQ 15

7o

! he cv!!strut L3on i>l lhe rag!..'!,~>up,',.s LhaL a1 1 aqua(s..nt storage cavities are se>>erat-.'.1 by a amoral slab.

Programmed a!!d rack m.".r.:lfac'u nd cluantiti "s

-. <<Sl;

~

="echtel.

Rc;..Ote S) ste;..s Co poration (P:"iR) the r.r, ':"sures t".,at c ~<<,".ct P>or 1 lccatiors were pl es'-nt

<<n acco1( "nce with t le

'4I "echtel c",~.".! i:"y':.ss>>3:::nce

'.t PM's i~.ciliti s> ~er3ried i!;.i li,i:j<<'ll<ativn of f:

~ ( s gA program.:~

< so, i'urging fah 3. 3ca!

3 on P;YJ.

c".'.""fv

~

addlt3.onal 3ni><<3

. '. ~.'.",lt ver3.:!.catln!1 of P.'-".R s

r~A program

~

Doer.. '::..- ion rela t "d to IN sp"nt fuel st.or='e racks is locaLed;:t t",.e P.':s(u-'.

na site.

Periodic veri ":.~al i~n of P~ron

.."". ".:,:;::..Ss wi11 be accomplished i:". n'.:.gh an irservice inspection pro...:.=z utilizing test coupons.

T!1e:-f". -ctive!:e=s of l!

-.i='nt fuel storage rack is determined through per'odic weighing of test s'pecim ns.

The test specimens are contained in the test coupons.

Each comporent is anodized separa ely.

The top and bottom grids are m chined to mail!tain nominal fuel spacing of 6.625" inches center to center within th rack and a spacing of 9.375" inct>~s between centers of c vities in adjacert racks.

Poison cans

".est in pockets which ar cast 3.n ev r) '.'l!llr cav3 the grids.

This alrallgement ens'>>

s that i.o struc~" ral loads will be i~ posed'n the poison cans.

The pois:n cans consist of L;o concentric s~luare tub.s with fn';-r Boral plates loc ted in the arnlllar gap.

The Boral 's positioned so 't o;erlaps the fuel pellet stack l~.-.-lh in the fuel ass..mblies by 1 inch at the top and at the bottom.

The outer can is for.led into the inner can at e !ch end ard seal welded to. solate the Bnral from the SFP water.

Each can is pressure ard vacuum le k tested.

The <:rid str!.Ctu.es are bolted

..nd riveted together duri!lg fabrication by four corner an"les and four side shear par.els.

Leveling sc:ews are located at the rack corn~ rs to allow ad'.ust.;".. nt for vari-.ti!ns n

pool floor level of up to +.75 1nrh.

To maintain a

fl!t~ unifo!.m colltactarea

~ tile b "'-.'ad at the l6

lp

I s

a>ol L'..!s q':!"" i's

'~ ">

'!t ' <<ct 7 ir -~! ~ "~'n t'h~

4 ~

afloor to:.1'!!. for coo! ant

.-'ow under t-e racks.

~ + o> l,. i!;.,',

~

v.:

~ e

.or, coo:-...t f.'.

j n '.;:

c"r:,"er cavities et>;>>.! n the foot assembly:r:d th:.. bottom of the casting.

V'se are top entry racks d"signed to maintain the..p;nt f!iel in boron-carnid

/anodized a1 '-ij;.uai po-::;on co.partments that pr. cli de the

,:ss.l i1 it~

i r ic:lity !!nder

! or:;sl:.nd '-.b:.orr,'al ocr!i:i"."..

! ".1 '.."; art is ~ro"i!:d <<lc.g

"..he the:",'..'~,'o!".'! of:1:terai a:".d bend'i.s;

',o~"ds to the fuel '.s a.<<3)l v dur lng handl j n -

a!id st:>r":.!e

~

T'-". we "ht of !:h~ ~,i'1 i y 15 s'~'~a! ted j!i a

~..'~...!be L

'iy the boy'l "i

The location of.

Ll'.e sp-.nt fu.-l st:o!

.-, facil"y !'i".!'n the s!'tt'.on c

-ix s

s'.".".'.~ in S-c:.

1 9 of "'e '">'~

FSAR.

The rares are connect..-d Lo wall ';..bedments on the pool wa],3s;.nd s!!o!;n in 75 ~R Z=::::.". 9.1-2b.

R ch pool h-"s

"=4 roc~:s

~or a stor-.g>> i::,:-..:.y of ?S-':0 fuel a)un~ 'e/a s -'..Jw les jl!!s 10

.",u 'izzy'.'i!~ ~ ~

'. i avi. tit=s Col

~,

stora e of.:":.ro'i i<"-;s,

'ol;.

.<<.!e ti."s,;nd defective f el con'..'.i,=rs.

The rack arrangeme>>t is desi=noh to;i; '.'nt acci...ntal insertion of fuel bundle/as.i:=:,ibli.s

'. -'.':een adjacent racks.

The design of the rack mod!!l,.s..nd their constr!iction rey>irements p.eclude tt e possibility that the ra~;ks may be put together so tl!at <<djacent fuel asseaiblies will not have a bo.al pl,;.te between them.

The rac.;s are designed., such th"t alternating storage cells contain poison.

The orientation of the r.: '!iles when installed in the pool, is such that the chec!:er.:oa'

~ pattern v'ill be r:3l <<ta" ned aci:a=s i".

bound"..! i os.

Tlie rack modul es are braced

+o fuel pit >'alls, such t!iat::!o"=aient are braced to th spent ii 1 pit walls, s!.'ch t!iat !:ovem.nt (i.e.,

slippage) along the module bo!'n<!aries is prevented.

6.3 Radiation Honitoring The t!aining and experience of the Radiation Protection Officer

's pr sented in attachment 3.

6.3.1 Perso'nnel iso.zitnri~n Personnel authorized to uncrate, s'".:;".y, store,

.",ud inspect new fuel assemblies s.!all car y p -.sonnel 17

~

~.

~e j

~

l>

(>n l Or>>l NL 3

o g

k

~ >'l J 3

2

.':.'.;: ~

. I

.ssenblv "/~nit:)r'. ~

F>>!Ch n>ew f'!Ql 2,':

<>""bly vil1

~ ">'ito!"d '!. r(" '>>l"ble alpha and beta contam !l::tlo!! i()llvvirlg ".n,)a ~ l;".illg.

In

addition, a beta-ga".>~a dose r(!te survey vill:>> ta!:Qn 0!l ('ach

'SS<.'. hl.)'.

R!!> or>>s of r"~>>1.s wil1 be r.> i>'Lain>.d in ';>.c>>> >.:.!!(.e '>! i.h s'".!.i'. n <>r.~..(>l:res.

6.3.3 A >'t'a.'ion! tor l.!!>

'~ ~

>l l>>

.ld

!!!o!~!(>(Qd> for r>:>,!(>':?b I Q

~

~ ! e al r"<!<etio.

1 ",'(

~ s f egucncy,

posting,

!!d re((>

p rfo.-aed in accordance winch

~ill

(,1 e

".a 1 L'h 1'iy s '

y J

'.:!> <re s The criteria f!Qo!!Qncy is occu"3.ng and fcoj!'Qncy vll re eel.pt

'4'h>:.il deternining the

!!>inimum area s!'. y based on the fu>>l >>andling a('i. i. '. Qs per ouuel 'ccess

'o tl!e area.

1 be 2 t;? r J::.i: ".!'! dur> n> ~er(>",s>>

~

. l!>~1 PC rSO >ne QCC,,'S at a rti n.;.!>.'1

)vs>en rece ipt,.nd inspec tion vor~ i" i:l pr,.

~, at

.>1

!aonitoring vill be perform>'d dal'ly.

Otherw3s monitoring vill be done G'.1 a v>-Q::*y basis.

6.3>4 Instruventation The following instru~>.entation, or Q(lu>ivalent, ai>ailable to support the receipt

d in~p=cti.n fuel bundle/.Sser>blies:

Tl~e

!lodel Ra.".ge Gas Flow Eberline FC-2

ÃA Counter P.Q::lo'Fable con ta,.",i<,.,n survey Ic niza tion Victoreen 470-A 0 r~Ji/hr-1000 R/hr Radiation level suriey These instruments will be calihrat>d

".".l a cu"-.rt> ly basis.

6.3>5 Fm r~ency Actions 18

1

~

<< i i ~

~

I ll

~

~

1 Cue 1

=', -k s d.+aged i

w

+

ii~ J i

l'h'SES Operatloj!5 S'xixt Su"e. v:""

0 '

aim.".t d

"ltcrnate is rcspons-;bio fox init-'atjon, di3'e tie:!, "nd tcmiination of any e:;ergency 305"..=nse.

6.3.6 Rei!ui st, i vz i <<'.0::.ot'n L

'1'i'<<." ""'1;ont "c 1 5 'i<<n'. ".ix

<!uring:";-eeipt, unlo: ding, j.'i<<-'01 esse;-L>lies i

..f led!:R",r>. 24.

'::i 5 a the..aturc of the iec 10.

an< stox age cf C a! >:

PRA<< i! 'i 1

(

-; '".5 rllc. ';>:i or i>e

".'.' t l.<>

'.:":1.

Co:..st!-..cT 3; n or co:! trolled 50 <<s

'.!!.-.1,.'cted or stox'ed 1 Xre PX'oteCt !on sys <<.Ci'ils 5'!<<! stox a<c>>'3. l 1 1.<<e c:,

<<I acl Ivxtxes on tne re.uol

< I !!c;ing flam,. ab1 0 mat

iot to pose a thxeat to

~<<.ria*ii..g io i,.

1 T.irior

. 0 !,"C" X".t 0f 1!g 1'ovr '.j!vo'vxng a

~.rxals l'i.ll 1i!3 ec:".~1C d

fl!Cl bc ing re<<et i ved T!0-

". c~i-:Til:;e <<1!scu:sion of the Susquehaj!.!a S'"S fire.:;ection

. Io-ram, 500 the S sc;uena:.na Fire Prn'ection Revie

~epor-.

prcviousl>

su!>."..it ted to the NRC.

F1 '0 5"pg

. 55'on cap..1 311t1cs 1Bportant to ncii'el reccx".>t aild s"..i=age are i'xen:iCied b low.

<<";Ilroad Axrlock ai!d Flois~t>>'a (EL 6>0'-0"-S18')

railroad ai: lock a.!d hoist>>ay rave

'. Cen desi-,nated

<<5.ire

=0.".e 1-(S:.e FPRR Su isection 4.3.13).

Fire s! ppr-ss on cap"<<'. i i'ty is

.',i,>lied '"v a!!to:-"..:!tic dry pipe sprinklers and j..anuallv ooe".atctl iire

"':,hting equxi<<::.;j!t consisting of fire hose stations and portab30

'i j<<Oui 5hA c',

~

".e:uelinq Fico! (i'L S1S')

}

I" fuelii:g Cl:<<>r has been desi".";..":. cd <<5 C1r "0:ic 3. <<A l,-.'

'<<R 5': ct i 0T! 4. 3-3-)

~

) iI e suppression ca..'a13i 1ity is =!:.-1.'"d by

.;an

:ally operated hose stat,30",ls eguxpped ',th 5 xi

.j~ si'...'-: !.:.>i""lcs (S

e Attach...ent 4).

19

~ ~

ll

~

~

~

oz t'nc..::ysic::l ',"

~ ity

,: ~)ication lus l~ "on;~ado b) Ponns) lv;:.ni

', "' ', n fall lo:l1'nsUro s fol rllcl ~31

>1 )w

< ll)vl)3 fO1 telo l i1 10(1 1,*V

') '

>i J ~'~' 'l

< ~ '"~('~'P l

)

~ 1(,, ~1 cR -.".-r. (

~

~ i n,l i n i, iO'a a.'n

(. ~ l1'OJ 1llca~ inlvl.l tnQ

~

~ 1 1n 0 tll';"'l'.c.tol.

~

Px'oof of 1 i.n:.'ncl Pl

~""o

~ I ~

o

"-, l,l;nt Co:::p, ny to I

p'9

)

I 1 1 l g

)

i jg.l 1s I1 ",ng 1llIl '

lv'd to

.'SY'.'XIA i'" i'.2 fl j,iC'i7 CO.'JPAXY

~)i ~ I

",..ln

)4.

C'll"t '.5

."-.;-.,~.ny=.';.~,::.ci Cons t1 llction-Ãucl oa1';-:.

j-'=":S 20

I s

~ ~

~

~

".i I II

. ~

' "i II w ~

~ ~ I ~

~ I

~ I!

~ I I ~

~ IL.

~ g(

UHEC.<= Z, '-"0 Fk covcR OE7 A/<<

rr/

V' y

P S: ~SOVFI!A I.'uA S I CA:.l ':LECTRIC STATIQ'iXI'!

S 1 A,IQ 2 tlhkL AFc

> Y ~

~LYSIS R~?ORT i4-'V I:Uci VAULT C0 VE R [3.:TAI I $

QEC7 lOrV

4 L

6.1 5" 5.215" i, JID 0 I 7<<

Il?""C I'LOINS

~ I

~ I I rl I

r> sp 0.0475" 5.12"--.

!jul 0.125 x 5.250"

~

- ~-

6.625" 7.093"

'I

! ':.. l::::.Aii:.'ASi'I=.-'.M bL?!CTl'IIC STA I IOiH I 'I'!ITS 1 AND 2 i I" '

I. F. iFTY;"".I'!.LYSISIiEPORT

'"-:;-=:RKNC=. C.'SZ p'=g

'". ='.G"-

OXSO.t (;,q F IGI i3'" 9.1-'b

. >::nnis J.

Tr(>l?t

! '-'"."":."3 NOH':

--'i".ion:.-'cti..e V> al th 'Phvsics

-:. 'rvisor i'i nc.'.) Jvania ower g

>.~. -"~t o<4gany Fu, r.!~l'aa S."'S

ip 'Les

>ocailon J'!!ly 31

'f979 i;o Pres S'q

~a..na Steam le= ".x c ~tat oa - 7"r~icz, -A Supervise Health Phys':s Section acti~

~ "~..=s.

??erect dev<:.<..::.=t of Health Physics Prog's and'Proces!:':i.s to a:-~ere '-;"1-..:.t"-.

i;ion of ZS.-'32 commitments and regulatoA) xc ~jul j ants

~

S cc> ioQ, i)f 6 aliI,ied

~a alth P>hysics perso~>el

"..!".0

'5?.'.p3.> '.'~ntatio>

<?+

>'uired tra'ning pro~ra-..s.

Develop equi.'..">'t a! d ?..an~c ->ar ~.:d-"ets l.'o meet prog am requirements.

Assist in E-.;er."ncy Plan <<ud

..~lementing procedure development.

Serve as

?a-...her of Cn~=.orate

,Q.<iQ.,eview Committee, and Radiation ifonitoring review >'v >:!.'.i'ice.

'os 'I g's

>.'ealth Physics Engineer P "~sylvania Power 6 Light Coma,!:~y Susoue! anna SES Dates:

!.'arch 22, 1976 - July 31, l.'9

":.neat o: July 12, 1977 to J&y.M, 1979 Si soueha~~a Steam Elect ic Station - Be~.-:ic,, PA D'-'cIQS-arch 22, 1979 to July 12, 1977 Susquehanna Steam Electric Station Plant Staff 5:o North Ninth Street, Allento m, PA I

D veloped Nuclear,St'ation "as low as'eason"ble.

achi v=..)1 "

(>ThKW) Program.

Assisted Health Physics Supervisor in the eva3.>>

nation and/or direction ox Health Physics Prog am and act.d for

>'alth PL) sics Su e!.'v sor in his absi !~re.

Partici.)ated

'> Q preparation of CESAR Section 12 d veloged

.alth i)'.ysii'. pro-

.cedures organized the external and." ";e:."a ra~ iation '-..',?)osure

program, valuated iu se 1ected St" t).on

>;.. ~.':h:::,'. ~.cs

-;! )pment, participated in vario: s Health Physics

'.I'!:a'ning Progra.

- for 8!"<tion personnel.

.-rved as C". air->an oC ~'>>q ~t'.ation 5 '=%4

'>s 'pieg Co

>ittee D3 rected ej>~~ge>{ )

s':0' pp Q>'

~1

> p Qo lt>>

>'.oring t, ms in rc.s > ).".se to V~'arc13, 28 p,?. '9

.'>;.c:Ude' at "ile Island.

j)g rp~ 1 of 3

2ox3

<<~~.. i.

~ vu.

ss> stant Eng'I'hl Qr

)ucl ( pr Nuclear. Station - tfetropolitan Ji i tF."5 ~

Zocp>> on'arch 1,

1974 - Harch 12, 1976 Three Hile Island Nuclear Station - Hiddleiova, PA es D>vcloped Health Physics procedures and i,.p.e!".'=ntcd x~.porting 1

'I 6

7 z:.::u~ reagents.

Per or-"d rele=s-rate, and;o-c.";..cu..at'.-."s.

enented training progr:!~~s f>r Station p'r ". -=

and:,; d/

C!'a. Techn cians.

Organi.-.ed radiation e~~~os::"= orcgr;n and

.di~:cted in-house TB operations.

Implement

~

Physics Proozag throuoh first line s!-'.'.!

~ ~ s'..on of .d/

C~,cB TCCLQl.cians

~

Supervised technxciails an<i. ass'"..t d '..i th

. !!:.~1th Physics evaluations through initial fueling, st."r':;p, rz~erous r!aintenance csti=ates for various aspdcts of t.!e first refueling outage of Three Hile Island Ui>>t X.

..:..oted In J nua!g, 1976

< o the p: sit on of T:.=-.'-apical

, 3,s III.

= os i ~.ion: "-u'alic In o~t!ation Coordin;-tor Dates Location:.

June'l, 1973 Harch 1, 1974 Three Hile.Island Nuclear Station Hiddletovn, i".A Dg'.'s lectured to public inte est gro.!ps concerning va...-ou" asp: cts of THINS !:ith ev'phasis on enviro"-.ental and 2=-.".

~'.h Pi)ysics concerns.

4

~ f, g I 4Q ~~

~ glgtQ lc59-3973 Albright College, B.S. Physics.

1975 197S 1976 1976 1977 tg77 q rq 1979 1979 Eealth Physics Certification Training/Refresher Pena.

State Reactor Operations Course Resp:ratory Protect on Progra...s and OSFK SSES Rad'ioactive Vaste Treatment System G". Boiling Pater Reactor Technology PiX Rad ological Training fox Ha~t nance Hanagers and

'c~ ~inde rs G" Radiological Engineeri g Course Susquehanna SES Plant Systems Cou"se.

Packaging and Transportation of Radio ctiye 'naste

'~::=.~S.GNARL SOCI"TIES:

2 "1th P'-rsics Society Dc>.3!:are Valley Society for R diation Safety

'P:: e2of3

~

~

3 o

3

.:;C" Vz36 P.DYAiio.'7 A!aoUQL 'ocation Duz -..On

-f Use 7'~" oa of U5Q 1

2 1sl.on) l~n)

,. i5. on T=ace-Vj l,oCi!Vie Three Hile Isla"d.iuc1. <<a1:

g<:-'t'. On

'gaea)

S R-"a~toe. ilealth PLi) Si CS

.'. ZO.- 1:c=Q

~

~

~ ~

~ ~

\\ ~

P,-..e3of 3

LI

/'C.

I Jrvrvf I

l I

i I

i v

v I'Ihl I

II I

I r I'

L I

~vrrvrvIL a

c,"'- W~

J' LL L~L Qs '

~

~

J I

I

~

. ~ ~..-

l~

~

~ I I

~

I v

~

~

v IQJ

~.

~'

~

~

~

~ ~

Q CJ

( ~or fv~ 'hL I

I

~

ft' hr r ~

~

I

.vr vv f

~

~.rl Z

'IC G.

I

~J A L'5 0

. WV ~I:ILII C>>

Cs--

I P ~ v II

~ hf'r ~

~.

Lf

~r Lv ~ r ~ ~

i

~ r EI LITre r h I rr Qr v

S vI I

'I

~

~

C

C

Ci&

C V '

CI C

p

~

C

", ~"

C

~a Cght I'

~Q,, '

r C:LlLC>>

Cla.>>

~ '

V ~

I I

~

i l

~ % ~ lr I

Q 1 I ~

I I

\\ l ~ ~

I Cl "L

>>C 4+ PC L 5LND

~ l>>C Ct r

'I a

+CLC~T CP<< I>>

'4i.;j

~ r', Ji~~

r: r4 C

PL l I

+

~

C%

vr, l,ll CM vl v

~ C'OL)

I'L CS L rrhhC rile

~

~

l

~

t

~

I Il 4 ~

r L

VA I'C I ~ tl K CAL CL>y lL rsLLL lt IL14CIA ll ( r (L I'",l<<r ~

L r r>>A ) tt>> 'L PC4%

C

<>VC

~ Eel l I I

C 4 LC Q

>Alt>>

V>>th<<'l = \\

Ml~l

~ ~

~

f vr I v<<LC CT4 '

'lcr'."K.Cf CM I

J