ML20040F672

Forwards Request for Addl Info for PSAR Review.Items Reviewed Include Seismic Input,Seismic Sys Dynamic Analyses, Reactor Internals & Sys Quality Group Classifications

ML20040F672
Person / Time
Site:	05000000, Limerick
Issue date:	03/27/1971
From:	Case E US ATOMIC ENERGY COMMISSION (AEC)
To:	Morris P US ATOMIC ENERGY COMMISSION (AEC)
Shared Package
ML20040F238	List: ML20040F237 ML20040F625 ML20040F628 ML20040F634 ML20040F638 ML20040F642 ML20040F644 ML20040F646 ML20040F647 ML20040F653 ML20040F659 ML20040F663 ML20040F669 ML20040F670 ML20040F672 ML20040F674 ML20040F684 ML20040F689 ML20040F693 ML20040F699 ML20040F702 ML20040F706 ML20040F709 ML20040F715
References
FOIA-81-385 NUDOCS 8202100083
Download: ML20040F672 (11)

Text

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-~4-1 Peter A. Morris, Director Division of Reactor Licensing E

y LIMERICK GENERATING STATION UNITS 1 AND 2, DOCKET NOS 52)AND 50-353 t

~

The incomplete PSAR information submitted by the subject applicant has J

been reviewed and evaluated by the DRS Nechanical Engineering Branch.

An interim evaluation of the information submitted to date, including ~

?'

Amendment 4 to the PSAR, is enclosed. Tentative conclusions are en-g closed in parentheses; the material in brackets provides a sumary of y;..

actions to be taken to resolve open issues.

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g,e-.d s;m i '"

.f(r E.G.Cr" k

Edson G. Case, Director f-g g,,_

.p Division of Reactor Standards

Enclosures:

R Interim Evaluation-Mechanical 6

for Limerick 1 and 2

%pg cc w/ encl:

S. Hanauer, DR Ier.

R. Boyd, DRL R. DeYoung, DRL M

D. Skovholt, DRL

{

R. Maccary, DRS f-f D. Knuth, DRL

.f l

D. Lange, DRS g

K. Wichman, DRS f:

K J. Knight, DES q

8 Ah

&;9 8202100083 811019 PDR FOIA 1

ZITZER81-385 PDR 4

o.ner >

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_.....DRS A.

RS*

RESS W )eary

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sunaut >

y 4

part >

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• U S GCv8 '*8 '# ****#* 0" *" " ' ~ ' ' ' ' ' '

e Mc-516 (Rev.5-53) MCM 0240 n*A.

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o REOUEST FOR ADDITIONAL INFOPATICN

)

<.q 14

. LIMERICK CETEPJ. TING STATION l' NITS 1 AND 2 qda f.h t0CX2T NOS. 50-352."D 50-353 Wu ta

?:

W h

. : :=le Intut Tc.:. scis=ic design response spectra sub=itted produce a =agnificction

_d..

Mc::cr cf 3.5 between the period rcnge of 0.15 to 0.5 seconds. Pro-Nfe e

p, :.d structure cad equip = ant dc= ping facters are in accordance with Y

m M.p.

these racc== ended by N. New=crk. The response spectra derived fro

' 4.t.

tic tina histories to be used for design cre cdjusted in a=plitude and dg;..

c M

f..c.utnc/ to cnvelope the respense spectra specified for tha site.

k'e

~6.{

q.2 -

h.

.nc cur scu =ce censult nts concluc.e that the seis=ic input criteria M

y,c g

proposed by the cppliccnt provide an acceptable basis for seis=ic 5

A l:',)

E=1 3.

/

8 m

m..

W (Tha cbcVe ccnclusion assumes that the applicant vill docu=ent the

' ]

x r

.p.

cgrcc=:nt with the s:cff concerning the response spectra derived fro:

gg.

I l

c

~

the ti=c history.

In addition, the cpplicant has received our questions jq.

.9 l'

M

casting identification of' cll; Category I structures, syste=s, and y

i y

,4 c;=poncnts, de ping fcetors to be e= ployed, the'=ethods of dyna =ic Tg y.-

.r. lysis, cnd the associated str ss li=its.

No difficulty in resolu-e.

a rien of these arecs is e: pected.

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r.-

I

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.bJ I

9 E-ic-.ic S 7 sten t"nc=ic Analvses w.., +

,-c

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..:. :.1 respense spectru: =ulti-degree-of-frcedc= cnd nor=al mode-ti=e M

vp*

h:.:.tcry =2thods cre used for cli Cctegory I structures, syste=s, and jg I

1

'. (

p.

g

%==4-

s o

e N

?-

f%

_fY ' th

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1

n-S f--

m.

N

^Y

~2%

v

_2_

rw D*...

wM.

cc=p:n= 0.

C:.verning response per::eters vill be co=bined by the

,!w w

squ re root of the su: of the squcres to cb: in the tod=1 ::ximuns 3S:

w,* '

.4 y

rica the ::d 1 respense epcetrum ::.thed is n:cd. The cbsciute su.

pr t

p..,

ep.

cf :: p n :.s is used for clescly spcced frequencies. Floor spectra t.,

y

-q.;

input to bc used for design cnd test verificction of structure,

[h t.

~'

-n W;

f :: : cnd cc ponents are generated frc the ner:cl rede-ti:2 history

~M W

thod. A vertical scismic-cys:c= dync=ic cn:1ysis is being c ployed

-C,..

q' s.

in licu cf c ccnctcut verticci locd factor for cil structurcs, sys:c 3t.c

/

4L

{7~

= _ cc pen =:: uith natur:1 frequencies grec.:cr th= 20 F.:.

• c cad our y,

p.

ic cre.:ul : ts conclude th:t the sc.icr.ic-cys:c dynetic 2thods wm c.,rc:aure.:, reposed by the cpplic=: p cvida = ccccptchic be. sis W-

1. 1 v.

fcr tha :._ :ic danign.

W,,.

w

v.. ;.

3-t

" cc'cr

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.ic Sveter Sciscic. 0.cratine. end 1.OCA k.civsis

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4@'

x..

(5::. tic, cper: ing cnd LOCA loads are prcposed for the design of the

-25 a

g%N

.n.

r==:or in::.rncis. Seismic loads will be determined by a response g.h

&w

.:p.::run c clysis using the squcrc root of the su of the squares p

p.

4 (r.iS) ;.:.::.cd for cc:bining todal responses. The applicant has been um

.qu = : = to dc=cnstrate equivalenev of stctic loads to the dync=ic C

N.

Ic=:, cb::.ined fror the cppropricte dyn=ic sys:c analysis and the M

a cdcqu.cy cf the SRSS =ethod for cc bining loads cciculcted at closely M

spr. cd :d:1 frequencies reference c.uesticas 15.19. 15.20 cnd 15.21 of

_st th: 7:.b ru:. -; S,1971, DRI. letter to the cpplic:nt. We have hcd further

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.=:. crc ccncie:cnt with thcsc ceceptei. for cil recently revic.cd plants

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cf :hi; :,-.:. cnd for: cs acceptchle basis for the design of the Reactor

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N.

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f.

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?he cente. ive conclusion indiccted by cbove pcr:grcphs anticipates w"g I

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, ; :.. C. ' '. c . - m..' 1.h c =..c g - ' - o. y-E the :cccc cnd juctifica: ion for these criteria. Question.15.22 of the

]=

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T.bruc y ',1971 letter to the cpplicent identified the specific criteria his

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l C:.r.psr c. : cf the =cchcnical fluid systers of the Engineered Safety Systc=s, c::clu:ive cf the recctor coolcat pressure bot:.dcry, will be 1

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