ML17255A301

Discusses Analysis Used to Meet Current SRP Seismic Criteria for Refueling Water Storage Tank (Rwst),Per SEP Topic III-6. Preliminary Results W/Input & Acceptance Parameters Encl. Final Analysis Will Be Available by 830715

ML17255A301
Person / Time
Site:	Ginna
Issue date:	06/16/1983
From:	Maier J ROCHESTER GAS & ELECTRIC CORP.
To:	Crutchfield D Office of Nuclear Reactor Regulation
Shared Package
ML17255A302	List: ML17255A301 ML17255A303
References
TASK-03-06, TASK-3-6, TASK-RR NUDOCS 8306240311
Download: ML17255A301 (42)

Text

REGULATOR NFORMATIOA DISTRIBUTIONEM (RIDS)

AGCESS ION NBR; 8306200311-DOC ~ DATE; '83/06/16 NOTARIZED!

NO DOCKET

,FAGIL!50 240 Rober t Emmet. Ginna Nuclear '~Planti Uni]t.1i Rochester G

05000244 AUTH'AME AUTHOR AFF ILIATION MAXERrJ ~ E ~

Rochester Gas 8 iEl ectr ic,Cor p,

'REC IP ~ NAME RECIPIENT AFFILIATION CRUTCHFXELDrD~

Operating Reactors Branch

'.5 "SUBJEOT: Discusses -analysis used <to meet current SRP iseismic criteria for,refuel<rig water storage tank (RHST).per "SEP Topic III 6, Pnelimi.nary resul~ts w/input '5 acceptance parametens encl'inal-analysis will be avail-able, by 830715, DISTRIBUTION ~CODE!

A028S (COPXES -RECEIVED:LTR, ENCl (

SIZEL"

,TITLE:

OR Submittal:.SEP 'Seismic 'Review NOTES:NRR/DL/SEP icy, 05000200 RECIPIENT ID CODE/NAME NRR ORBS BC 01

'COPXES LTTR ENCL 3

'3 REC I'P IENT ID CODE/NAME COPIES LTTR ENCL INTERNAL:

EG u 00

,iQ 1

NRR/Dl/SEPB 14 RGNi EXTERNAL; ACRS NRC PDR, NOTES'0 02 6

6 1=

1, 1

LPDR NTIS 03 11 1

1 TOTAL NUMBER OF COPIES REQUIRED; L>TTR 17

.ENCL 16

gP) k y~gp

<<I

~

i <<c ~1,,'i 7.,

j q

1 Pip I 9 "Its~) f 3l" i fei~tl l >114~ Jg 3'lA.q 3 C ~ ) Dry ) >,s~

i")g T<i,'i [$

~.,

C l I )Af I' e~1A 2 >t~ l'I r,

~ll )Wc~ 5>) )

q J,

y'fey j1 I~A ('q 'l) f 4'g f'1 >1<A 3 <<A

<<'~J "J~l QQ f~ ~)jf

,I'~l 1

~

fl f "J g >'I

~ j,g>>

Y,,

C'~5 t l t

II 4h 'Ly IW $ '( g

~

il 5

~

) e '~ a 1 "<

fy J J j 'f

( >'f>>,

i J

i,f I'>>'pqw I ')fig

'> ~ps c,rey~c. iq,

"~~', a~,p, r~l;, T j ~,'>>

f 9l)I 3

'I<

9 O'S Il /c i i) qg) f r.p

(,q~pg.~

q~pg) ~)~) f()~qy,)~

~i> %fly X>4 r~4 f t:~'x l g l<>f1 f,>If f 93'5

~ ""lb ~>k'~

y )

a f gi I 'i~

~(, g4 f f t<-,,

y iylqq>y,

<<e ~ ~~~~>>~+ ~~~'~

~

~~

~

~

<<f <<o

> ~Y~

J

~ f'"

I JI ll k

~><i shl

~

a

$ ~'I r l i <>f f'<<(>>Tr J

. >r~

~ ~r~".r.>~'.

4

~.: f~ f 9 r

~:

~ II'f 7

'i

,vol

~~ ><',~ l,X,<~., 3f r,;,

IJ ",~;<f )

l f 'i fg')jl f'~

Aie $

)

<<p C'

<l <fJ<~<

A)A

) f

~'

'I y

J l

pi%

c' l

A' I

ys I~

4'~,",X 5>>

'l,i,4 ill "g o J~~'1

< f X s

~..ff )>>

N~ t

~

~~1

~

4 l

~

~

g 1

g AJ 3

+>

<+ )g

'I

ii l h

l t nzrizrrrI,rrrrrrrr rrrrrrrrrrrrr'zsrr I

rrrrrrarr ROCHESTER GAS 8P AND ELECTRIC CORPORATION

~ 89 EAST AVENUE, ROCHESTER, N.Y. 14649 JOHN E. MAIGR Ace Prodldent TKLKPHONK AAKACOOK 7ld 546.2700 June 16, 1983 Director of Nuclear Reactor Regulation Attention:

Yir. Dennis N. Ciutchfield, Chief Operating Reactors Branch No.

5 U.S. Nuclear Regulatory Commission Washington, D.C.

20555

Subject:

SEP Topic III-6, Seismic Qualification of Tanks R.

E. Ginna Nuclear Power Plant Docket No. 50-244

Dear blr. Crutchfield:

By letter dated January 14,

1982, RGGE stated that because the RWST did not meet current Standard Review Plan (SRP) seismic

criteria, we planned to implement modifications.

Since that

time, RGRE has undertaken another analysis, using input criteria and acceptance criteria formulated for Ginna and other SEP plants during the course of the Systematic Evaluation Program.

The preliminary results, together with the input and acceptance parameters, are included as Attachment A.

As denoted in that

analysis, RGEE considers that the RWST will not buckle, and should be acceptably anchored as well.

The final certified analysis will not be available until approximately July 15, 1983.

However, RGSE will commit to make any modifications deemed necessary by the results of the final analysis.

In RG6E's April 11, 1983 letter, we stated that the sodium hydroxide tank did not meet current SRP seismic criteria.

However, the modifications required to meet current criteria were simple enough that the performance of a more refined analysis was not considered warranted.

RGGE thus committed to perform the modifi-cation by the end of the 1984 refueling outage.

For information RG&E has included, as Attachment B to this letter, the design criteria used in the'nalysis.

Finally, in the December 1982 Final Integrated Plant Safety Assessment.

Report for Ginna, it was noted that the only tank of concern with respect to flooding of safety-related equipment was the 75,000 gallon reactor makeup water tank.

A more detailed review of all tanks in the auxiliary building has disclosed that additional tanks should have been seismically analyzed, since 83062403ii 8306i6 PDR ADOCK 05000244 P

PDR

t t

J

., ROCHESTER GAS AND ELEC/RIC CORP.

oATE June 16 198 Mr. Dennis M. Crutchfield SHEET NO.

their col lective failure, although not anticipated, could cause flood-related damage to safe shutdown equipment.

The entire list of tanks, their capacity, and seismic qualification is provided in Attachment C.

Also included is the net floor area of the auxiliary building basement, and the limiting height of safe shutdown equipment.

Based on this evaluation, RG6E has concluded that the three CVCS Holdup Tanks should be seismically qualified, or prevented from impacting the safe shutdown equipment in the basement of the auxiliary building.

The schedule for providing our resolution of the seismic qualification of these tanks is July 15, 1983.

Based on the results of the analysis, which will use input and acceptance criteria previously found acceptable for SEP review, RGGE will modify the tanks, or prevent the content of the tanks from affecting vital safe shutdown equipment.

Very truly yours, Jo n E. Maier

I I

P r.

~

4 f

1

~t K

7'TAC H NAP7' h

W SUBJECT SHEET OF JOB No.

BY DATE STEVENSON R ASSOCIATES 0 ttn&ct&uct.mechonlccl con&uttlnp enp&nee&&np rum REV. No.

APP:

CHKO. BY OATE C7 P 0 S+0 &&J MVC~

&AJ l/~

TD

Ih A

s. a '~- s f',, t4 s

I J

r'

O',V ti g

SUBJECT SHEET

~

PP JPB No.

STEVENSON 8( ASSOCIATES o sttoctvtot.mechontcot consvmng englneerlng tttm BY

.CHKD, BY REV. No.

DATE DATE APP:

5/Q /IJ G

(I

/0 rA~/7Y C~g i~Q I

8dsr sod

.r -j" WD/-t I 'l I

(I C CIO<.

D(P fh/t ~y=

j I

j I

C.

I

/C.)

n S HOVl.>

h

O STEVENSON 5 ASSOCIATES o siructurol rnechonicol consulling enpineerlnp rem SUBJECT SAEES=

REV. No.

APP:

SHEET

+

OF JOB No BY~~DATE Q+~+

CHKO. BY DATE

~.Q ~~.P ~r/O hah

.+l~

. Ir-'

0 g ~~~

I

~W sT J~

'V! or aI

'C e

aIU a No, 4

rEEr 11 5~o V2n."

rl no uc~5 V

~ L.QvQW Ca 4,<

SI 88'X' V6i)<

..Cl

'IS'r I.F5X

~.IAIDO

~c OV oF: SI $t I i, I

< 4'j).,'I.,EJ.

gQu~

1 T YL I 1

14 I

.<0 C ICHT

0

~

~ 4 I

gt

STEVENSON 8( ASSOCIATES 0 Etl<<rct<<rrol.rnechonlc<<EI cons<<rlt<<ng eng<<neenng r<<rrn SUBJECT M~Wa=o~=

REV. No.

APP:

SHEET~ OF JOB No.

ST 32~OATS~

CHKD. BY DATE P=. /

R) 5 S<

.Sbp

/<<.

a j

<<ft b

U UQ!

N PA-n5V~

W&gC~

.t-.~&I.t-av c OD~

l 0"0 EAUF.+

)

c~

G~~o~~

<<t~+

E SI~~

I~()

~~~I.c-t ~ iI<<t.~~o~ <<+pf-c~p

g ~

I 1

C

t 0

E K

STEVENSON Ik ASSOCIATES 0 Strtrctrtrol-mechnnlcol contuttrng engrneering nrm SUBJECT AEV. No.

APP:

SHEET A~OF

, JOB No, BY ~

DATE ~E DHKD,BY DATE (x)

Ids A~73~D I)c l, 0 fo

'v7

/NI Art 7

5 1

5'p +t" h~V

]

~L c~~O.lv ~

/s 0

~

h

~ I Ir.>>'(

gl

RHST Information

Pump Inlet Nozzle

I

- ;10% Level:

244'6" I31% Level:

262'0" 237'8" Tank I.D. =

26.45'olume/Ft

= 4,110 gal.

Volume to 'Pump Inlet Nozzle

= 6,165 gal.

Volume to 10% Level '=

34,250 gal.

olume to 31% Level =

106,175 gal..

Total Volume = 338,000 gal.

Normal = 300,000 gal.

Tech Spec Min = 230,000 gal Bottom of RNST:

236'2" (s

g c, V ~

)l

~ l l:.

c iV P) ~

)I I ~ ~

VJ V)

Ll fj

v8g lcQH Fi'8'g L

SEE abc.i hlL RCQ

. 4 fPy R E O'Q 4'..n". DA

(..x

~ ~ r Jg

\\N r

I

~

STEVENSON 5 ASSOCIATES o EtntchtroHtlechonicol corouttinp enptneerinp nrm SUBJECT AN=

JOB No.

BY SL DATE~+~

CHKD. BY DATE

\\

REV. No.

APP:

~ p,rr~)

=

PSS A8.vv~

LNrtYD Jog t-0 6 oq (IQ' j

ID (a.s) 5olc log N

~

~

~

~

{ ")

o aerO aa ooae

~ ~ ~

~

~

~ ~

~

~

~

r r

~

y

~

~r

~e

~

'e e ~

~ ~

~ ~

r

~

e

~

~

~

~e

~ e

~

~

~

~

~

er

~

~ ~

~

~

re

~

4%o, Cg

~C q

~

~.

Qf

~

e

~

~

r 4

~

~

e

.c r@%~0

~g C~

~

~

e.

~ f 0'~

eoa

+

~

~

~ ~

o Orao

~ ~

~

' ar 0

~

r a

~ de'

~

~ e

~r

~

~

~ ~

r

~ ~

.c5

~

r

~

W ~

~

0

~ ~

~

~

~

~

0.0':.,"-

I

~ s

~

I g ~

7l l

't E

E Ie SUBJECT SIFEET~+

OF STEVENSON 5 ASSOCIATES EE EIFEECIEE EOEEheehOhlCOI conEEElhnP enPtheerlhP (tern G ItVAJA ~ME I REV. No, APP:

er M

EAVE ~S CHKD. BY DATE

.QLP. ~l

>x/)

~EE x

.Jg

./Ei'.'.<WW k~%)

X'V&

I IEte F+,j

~~

NOAFTOAl

+s/

+

3o R.

QOQ

', $3'.I J ~i E

I EFL

~ ~

I I

i i,,

~ ~

E h

t(

STEVENSON R ASSOCIATES o structurol-mecnontcot consuntng engtneertng ttrm SUBJECT o neVF REV. No.

APP:

SHEET 9G OF~

JOB No BY M DATE~

CHKD. BY DATE mo~

F F

F PFrt=~~l ltE

- DFAA r

SV L'u~~Y~

~<5 t

S'.7?.o I ~~

i Su~ m~

r '.o.orl V~

II4>>~

I

30. LV.

..l5 U c./L,L.~g,~.G.

~I4.C J&o I

Spic:,Lc f

t I

i~LJ

'l r>>i h.&lPC l~ t

~tv) i I

E C

g o ~~~>~~

~/o JoA w;p~ c I

I I

I I

% >A.>T(>>t(rr

~

t

.3'>>>

. gVC """

~ g( g

~t I

I l

Y A ~

i,t r

STEVENSON R ASSOCIATES a structural.mecnanical cansuttrng engineering twm ISV~.77M Ldyl.ltrbr!

SUBJECT

~O.II.O v 4.

g-b REV. No, APP:

I ~yt I

I SHEET M~OF JOB No BY ~

BAYB CHKO. BY DATE V~ 0 rsbt D /ht G

W/G/b / r~r I

I5DOAI I

r I.P.G

~oA I

I

.o&~

I

!I

~ ~

I gO

~ ~ '

~

I E

SUBJECT SHEET~~

DE STEVENSON Ik ASSOCIATES 0 ErrMChrrol-mechonlcEEI consrrlting engineering firm 8 0 C. r-I 'i@7 REV. No, APP; BY M

DATE~

CHKD, BY DATE C

1

~ i I

a

sr ~

l'he second

curve, ll prcssure load,"

lindcr subjected to l cornprcssion load

> the heads of the design curves of ders.

For inelastic

'ollowing the pro-

.ould be taken into

, nined.

tress for a

thin-obtained from the is obtained from

,li.

s rr r

tj4,

"'ir~

.;.) "

pg,

'rsi r

'lu where a,Lt CI C R sr is thc maximum stress due to the bending moment (e.g., the outer fiber stress). For elastic buckling, the plasticity correction term q = 1.0 is used. For inelastic buckling, the critical stress sr~ may be found by using the plasticity corrections suggested in axial compression.

Ifthe stresses are elastic, the allowable moment is Mcr = srRtrscrt Pressurized:

The buckling stress of moderately long cylinders subjected to internal pressure and bending may be determined by using Fig. 10-14 in conjunction with Fig. 10-13. Figure 10-14 presents curves IO 8

6 4

M M

No external oxial load I

pcO I.O 8

6 4

cs CI QIO 8

6 4

xlernol oxxt bod balances langiludinol preSSure load Pr prRt (Pftl'-axj Wu<~erv trrsH) p X3/

Stoblttty of Unstlffened Shells 235 The formula for thc buckling stress of moderately long cylinders subjected to bending may be written in the more useful form

ular cylinrkrs subj ected O.OI

QOI, 68 Z

4 68 O.IO, l.o 2

I 4

6 8 IO hjccted to bending lrc available in the figure 10-14 Increase irr bending buchling-stress coeflfcicnt for cylinders duc to internal Prcssure.

~ ~

(z~;

234 Structural Analysis of Shells WC1>~uric. P 1

I&)

subjcctcd to torsion and internal prcssure only. The second

curve, labeled "External axial load balances longitudinal prcssure load,"

should bc used to calculate the critical stress of a cylinder subjected to torsion and internal prcssure plus an cxtcrnal axial compression load equal to'he internal pressure load srR'p, acting on the heads of the cylinder. It should be noted that the pressurized design curves of Fig. 10-12 arc valid only for moderately long cylinders.

For inelastic buckling the critical shear stress may be obtaine'd by following the pro-cedure outlined in Sec. 10-3. The total stress fiel should be taken into consideration when the plasticity'correction is determined.

4t

~

8ending, Unstiffcned Cyl)ndcrs 1

Unpressurized:

The design-allowable buckling stress for a

thin-walled circular cylinder subjected to bending may be obtained from the equations presented for axial compression if y is obtained from Fig. 10-13. The classical theoretical buckling stress is I.O

.8

.7

.6

.5 O

V

~ ) ~

t Ct

~

r

~

~

STEVENSON 5 ASSOCIATES 0 stntchttoMlechenlcel cowvlttnp engineetinp fern SUBJECT C

REV. No.

APP:

SHEET~

OF

-I P.

JOB No.

BY~I DATE W CHKD. BY DATE

~.C nil nt OH C

I t

jl PT 7 't~

/+ Co'ski,'--

4

~405 oc t

d-

+

4 4

+

~ <

~ P I

~

I I

~

~ g

(

( ~

~

~

STEVENSON R ASSOCIATES 0 structurol.mechonicol contutttng engrneerrnp frrm SUBJECT REV. No.

APP:

SHEET~~

OF JOB Ncr.

BY~~DATE~

CHKD. BY DATE QiAQov'v

/

Ca bK

+, C.o CCrS I@OS 0(,

5i Hot,r O.~A II

~

.: CoS

STEVENSON 8( ASSOCIATES a EtructurotEnecnontcot consuiting engineering tirm SUBJECT BBEET~t'M JOB No.

BY~

BATE~~

CHKD, BY DATE APP:

V/

Alpha I8.88~~~~"

A B5 B6 10 PI~3. 14159: LPRINT 20 FOR I=i TO 90 30 A=I+PI/180: S=SIN (A>: C=COS (A) 40 Gl= (S+ (PI-A) +C> / (1+C).

50 G2= (PI-A-8+C) / (1+C) 60 B5=Gl/A 70 B6=(G2+2~Gi+S/A)/PI 80 A=A+1 80/P I 90 LPRI NT USING 100 NEXT I B-6" LPR INT Alpha L~

1.00E+00 2 ~ OOE+00 3.00E+00 4.00E+00 5.00E+00 6.00E+00 7.00E+00 B.OOE+00 9.00E+00 1.00E+Oi

1. 10E+0 1

'.20E+Oi 1.30E+Ol 1.40E+Oi 1.50E+01 1.60E+Oi 1.70E+01 1.80E+Oi "1.90E+01 2.00E+Oi

2. 10E+01 2.20E+01

2. 30E+0 1 2.40E+Oi

2. 50E+01 2.60E+01

2. 70E+0 1 2 O BOE+01 2.ROE+01 3.00E+01

3. 10E+01 3'0E+Ol 3'0E+Ol 3.40E+Ol 3.50E+01 3.60E+01

3. 70E+0 1

3. BOE+0 1

3. 'ROE+01 4.00E+Oi 4.10E+01 4.20E+01

4. 30E+01 n nor i.ni

'P.OOE+01 4.50E+Oi 3.00E+Ol 2.25E+Oi

1. BOE+0 1 1.50E+Oi 1.28E+Ol 1.12E+Oi 9.94E+00 8.94E+00

8. 11E+00 7.42E+00 6 '4E+00 6.34E+00

5. 91E+00

5. 53E+00

5. 1'PE+00 4.89E+00 4.62E+00 4.38E+00

4. 16E+00 3.'V6E+00 3.78E+00

3. 61E+00 3 '6E+00 3.31E+00

3. 18E+00 3 '6E+00 2.94E+00 2.83E+00 2.73E+00 2.64E+00 2.55E+00 2.46E+00 2.38E+00

2. 31E+00 2.23E+00

2. 17E+00 2.10E+00 2.04E+00 1.98E+00

1. 'P2E+00 1.87E+00 O<C>hh 1.49E+00 1. 4'PE+00 1 ~ 48E+00 1 ~ 48E+00 1.47E+00 1.46E+00 1.46E+00 1.45E+00 1.44E+00 1 ~ 44E+00 1.43E+00 1.42E+00 1.41E+00

1. 41E+00 1.40E+00 1.3'PE+00

~ 1.38E+00 1.38E+00 1 ~ 37E+00 1.36E+00 1.35E+00 1.34E+00 1 ~ 33E+00 1.33E+00 1 ~ 32E+00

1. 31E+00

. 1. 30E+00 1.29E+00 1.28E+00 1.27E+00 1.27E+00 1 ~ 26E+00 1.25E+00 1 ~ 24E+00 1.23E+00 1 ~ 22E+00

1. 21E+00 1.20E+00 1.20E+00 1.1'PE+00 1.18E+00 1.17E+00 1.16E+00 IRCaAA

H ~ BVC.~VL 4.60E+Oi

~ '.70E+01 4.80E+01 4.90E+01 5 'OE+Oi

5. 10E+Oi

5. 20E+0 1 5.30E+Oi 5.40E+Oi 5.50E+Ol 5.60E+01 5.70E+Oi

5. BOE+0 1 5 '90E+01

6. OOE+Oi

6. }OE+Oi

6. 20E+O1 6.30E+01 6.40E+Oi 6.50E+01 6.60E+Oi 6.70E+01 6 ~ BOE+01

b. 90E+01 7.00E+01 7- }OE+Oi

7. 20E+01 7-30E+0}

7 '0E+01 7.50E+01 7 ~ 60E+0 1 7.70E+Oi

'7.80E+Oi 7.90E+01 B.OOE+01 8.}OE+01 8.20E+Ol 8.30E+Ol 8.40E+01 8.50E+Oi 8.60E+Oi 8.70E+Oi 8 ~ BOE+01

8. 90E+01 9.00E+01 L ~ / / L>VV

}.72E+0<

1.68E+

}.63E+Oo 1 ~ 59E+00 1.55E+00

1. 51E+00 1 ~ 48E+00

}.44E+00 1 ~ 40E+00 1.37E+00 1 ~ 34E+00 1.3}E+00 1.28E+00 1.25E+00 1.22E+00 1. 19E+00

1. 16E+00 1. 14E+00

}.i}E+00 1.09E+00 1.06E+00 1

~ 04E+00 1.02E+00 9.95E-O}

9 ~ 74E-01 9.53E-Ol 9.32E-O}

9. }2E-Ol

8. 93E-Oi 8 ~ 74E-Ol 8.56E-O}

8.38E-01 8.20E-O}

8. 03E-0 1 7.86E-01 7.69E-O}

7'3E-01 7'8E-Oi

7. 22E-0 1 7.07E-O}

6.93E-O}

6.78E-O}

6. 64E-01 6'0E-Oi 6.37E-O}

l ~ J tC <VV

1. 13E+00 1 ~ 13E+00

1. }2E+00 1.1}E+00

1. }OE+00 1.09E+00

}.OBE+00 1 ~ OBE+00 1.07E+00 1 ~ 06E+00 1 ~ 05E+00 1 ~ 05E+00 1.04E+00

}.03E+00 1; 02E+00

1. 02E+00 1.0}E+00

}.OOE+00 9.97E-O}

9. 9}E-Oi

9. 84E-01 9.78E-O}

9.73E-01 9.67E-O}

9. 62E-01 9.56E-O}

9. 5}E-01

9. 47E-Oi

9. 42E-01 9.38E-O}

9 ~ 34E-Ol

9. 30E-Oi 9.26E-01 9.23E-01

'9. 20E-01 9-17E-Ol

9. }4E-Oi 9.12E-O}

9-}OE-Oi 9- 09E-01 9.07E-01 9.06E-O}

9'6E-Oi 9.05E-O}

9 05E-01

STEVENSON

5. ASSOCIATES o srruclurol.mechonicor consurrrng engineering tirm SUBJECT QQA

%45 I 17 REV. No, APP:

W SHEET MMOF JOB No.

BY M DATE CHKD. BY DATE CW 0

l l

l