ML20128K541

Summary of 850429 Meeting W/Util & Bechtel Re Soil Structure Interaction for Standby Svc Water Basin.Viewgraphs & Attendees List Encl

ML20128K541
Person / Time
Site:	Grand Gulf
Issue date:	05/21/1985
From:	Kintner L Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 8505310174
Download: ML20128K541 (20)

Text

K Docket No. 50-416 LICENSEE: Mississippi Power and Light Company FACILITY: Grand Gulf Unit 1

SUMMARY

OF APRIL 29, 1985 MEETING REGARDING SOIL STRUCTURE INTERACTION FOR STANDBY SERVICE WATER BASIN The purpose of the meeting was to hear and discuss licensee's presentation of its seismic analysis, particularly soil structure interaction, of the standby service water basin (SSWB). Enclosure 1 is a list of attendees.

Enclosure 2 is a copy of slides prepared by licensee and used in the meeting.

Licensee presented a description of the seismic analysis of the SSWB. The presentation included clarification of Licensee's January 28, 1985 response to staff questions on the method used to analyze soil structure interactions.

Major conclusions are provided on page 16 of Enclosure 2.

Staff indicated that the methods used appear to be acceptable. Staff's evaluation is expected to be completed in May 1985.

/S/

L. L. Kintner, Project Manager Licensing Branch No. 4 Division of Licensing Enclosures 1 and 2 DISTRIBUTION

5. Chan V. Panciera, R. II LBf4 ' (

b$ ht C:LB#4:DL LKintner:cl EAdensam g/,j/85 f g / /85 8505310174 850521 gDR ADOCK 05000416 I PDR

GRAND GULF Mr. Jackson B. Richard Senior Vice President, Nuclear

-Mississippi Power & Light Company- '

P.O. Box 23054 Jackson, Mississippi 39705 -

cc: Robert B. McGehee, Esquire The Honorable William J. Guste, Jr.

Wise, Carter, Child, Steen and Caraway Attorney General P.O. Box 651 Department of Justice

.lackson, Mississippi 39205 State of Louisiana Baton Rouge, Louisiana 70804 Nicholas S. Reynolds, Esquire Bishop, Liberman, Cook, Purcell Mr. Oliver D. Kingsley, Jr.

and Reynolds I?00 17th Street, N.W. Vice President, Nuclear Operations Washington, D. C. _ 20036 Mississippi Power & Light Company P.O. Rox 23054 Jackson, Mississippi 39?05 Mr. Ralph T. Lally Manager of Quality Assurance Middle South Services, Inc.

P.O. Box 61000 New Orleans, Louisiana 70161 Mr. Larry F. Dale, Director Nuclear Licensing and Safety Mississippi Power & Light Company P.O. Box 23054 Jackson, Mississippi 39205 Mr. R. W. Jackson, Project Engineer Bechtel Power Corporation 15740 Shady Grove Road Gaithersburg, Maryland 20760 Mr. Ross C. Butcher Senior Resident Inspector U.S. Nuclear Regulatory Comission Route 2, Box 399 Port Gibson, Mississippi 39150 J. Nelson Grace, Regional Administrator U.S. Nuclear Regulatory Commission, Region II 101 Marietta Street, N.W., Suite 2900 Atlanta, Georgia 303P3 Mr. J. E. Cross, General Manager Grand Gulf Nuclear Station Mississippi Power & Light Company P.O. Box 756 Port Gibson, Mississippi 39150

~

. ENCLOSURE 1 ATTENDEES APRIL 29, 1985 MEETING MISSISSIPPI POWER AND LIGHT AND NRC SOIL STRUCTURE INTERACTION NAME AFFILIATION L.L. Kintner NRC/NRR/DL/LB4 N. Chokshi NRR/DE/SGEB S. Chan NRR/DE/SGEB

-E. Fotopoulos- BECHTEL W. Mashburn MP&L-NPE Civil S. Sen BECHTEL R.-Burris BECHTEL E. Thomas BECHTEL 1

I i

t ENCLO5URE 2 AGENDA

1. BACKGROUND OF 'SSh' BASIN SEISMIC SSI ANALYSIS

2. INPUT MOTION FOR GGNS SEISMIC ANALYSIS

3. SHAKE / LUSH AND FLUSH ANALYSIS

4. EHS ANALYSIS

5. ENVELOPED RESPONSE-

6. SPECIF4C-RESPONSL TO NRC QUESTIONS

7. CONCLUSIONS J

l

j l

l CENTER OF GRAvlTY C EL109'.0" '

EL 181'. 0" FAN EhCLOSURES '

' 'l ' ! '

ll l ll 2' 1l 'N 1 EL 16 6'- O",

TOP OF CONCRE TE WALL EL 131*-O" ~~.

~~

g h c COOLING TOWER MAX WATER LEVEL EL 130*-6"3 ,, ,

FIN GR ADE EL 132'.6"g '

% ~,, _- "it EL 133'-O" 3 n

.- n 2' 3 EL 107*.6"g hp A T EL 112'.O*7

_ E E \ '

E E 3 _

-4

'T ir EL 8 2*. 6* 3

' s. p , - ,,-

n TYPICAL SECTION THRU BASIN ST AND - BY SERVICE WATER BASIN l

l l

FIGURE 2 2.-

i

O f

C 150' e 35' 20' 20' g 20' 20' 35' 1 )

L u IMIM Mimll f '

i

!. l N

= .

e s.

w l  !

. 1 l

l h  !  !

-o e -;;.

I i l h l l

I a l --

1 _ .-

1 .

k  !

e s.l-.

- 1 i

h L.p ,

PLAN AT EL 107'-6" ST AND - BY SERVICE WATER B ASIN I

FIGURE 3

~$

1 . - -- .- - - _ - _ _ . _ _ - - - _. -- --

BACKGROUND OF SSW BASIN SEISMIC SSI ANALYSIS EHS. 1973 ANALYSIS

- -l SHAKE /

NRC REQUEST I LUSH -;

' 1975/76 I FOR FRS STRUCTURAL REFINED I l

DESIGN LOADS MODEL g l 1 l NRC REQUEST 1980

& EHS FOR ALTERNATE ANALYSIS l REFINED ANALYSIS l MODEL l

l v I COMPARE I

& FEM &

60% EHS FRS 1981/82 Y

'I FLUSH NOT ACCEPTABLE TO NRC 0-

& ENVELOPE FEM ENVELOPED r FEM & = 1983 100% EHS FRS U

PROPOSED FRS l-i ,

t FREQUENCY (cys) 00 30 30 20 IS e 7 5 3 3 ta e 07 09 03 02 06 Qi CO

-x nuw ,m vvm <

37, p. .i y 1, 7 i gi h if, i y4 7 i y i; i f, _

i; r ug  ; gij x unY, n n xn v xnnwan mn -

~ 'MXA /\7AWh N/X E n /\ MA 'TNVi NHMA /T, X A Y 't W -

" /\fVN /VV YnV//X/Y'V't /V 'vYL W V//W l'/VN /V V't XL'D X X 'VXIM XW7x$//X X XX M '>C'M295//X'8X YX X X'k Mi "

,, d'vX)dNAMdW/'v^>()dv\MTj6$/Av^>O(NXX%

- M 8K d {'X' MMS 38FM4X'MfN6tW/ pix' WON

~~n-n + ~n--.- .--n -

,,f / M & % 4 6'SD df.') O %'#x AM" ? X W.t^4X5 x>ommenw e e c_Eoinx w e n ,,  ?'

. m.9 _____ _%

.N Y m _ L _Q M_ M #__

.L HFN'i AA /\ A A Y'M4 i N ///r M N E A Y'i'A 8

, x

- __A

. M A Q(Y X X V\ X X

• C'/% / d'k^t /VY< 'fbM/ / 7/D'fAf&'Y/f't X'RWs/ X /v V\ /V '/\

l &&/J'x)N XA X XW5%5f'>KU/ X . u 2 .mowxsa w6ww/.vX/1 X%'8?%6f/X1A newwwom Yx

( ig S5'$iV/d>l'M%FM&fAM'MX6MWA<X'MM64 wwm n,mwwwr e m >scemswanawa, EXX M 4 $ O f M /A C V A W 4>'6 R'd E'X X Ys' d' v>a> m #m>wnamcoxxxw)('4./#/>fWw nx

. _ h,%@ 1h, _ s _M M _Q @FG%

A N '/. A

- x _  %

~FN~~ - ,,/\ i '#_P/if/7J f \ AN_Yi A ^3Y,M ',N -~ -

/

\~~

1. VN_Y i A ,^ J ~s-VA W /H -

M/W/VW. /'s'i;W/X /YVi /VV't 'e^i'N 5Z 't/V'y X %'Vs Yt'h .

• !C9'f X W f // 1',W/ )^X'in YXlXi fgNg X'i,X >ry Xi V W Q' mow m mn w n wnwv:w m,

.WSXW > [ 'x N Y N M G S hi d d M ' W ) D L.

w w w / a.N<cMwNx Y x vMnhnK/ a kw a x w n r~m m x

=Y>NV/44 /#r'5fD/I '/>Nk\4; /A'NKbtVXMN'!M vFNXh4

,! O C /' Y 9 % f ? ki M O Is'X 9 J:IR $ D { K W X W M 1 25('X N g

.M MGM%iMMMA&MM. .0. 0. _ . . .

PERIOD (secs.)

MISSISSIPPI POWER & LIGHT COMPANY GRAND GULF NUCLEAR STATION DESIGN SPECTRA FOR SSE

{ UNITS 1 & 2 FINAL SAFETY ANALYSIS REPORT FIGURE 3.7-1 b5

,.-..--.-,y -.- - - - - ,,,y , , . , . . _ - . , , . - .- , . . . , . , , , . . , , - -

GGNS SER SECTION 2,6,2,4 SAFE SHUTDOWN EARTHOUAKE IN DETERMINING THE SAFE SHUTDOWN EARTHOUAKE WE HAVE FOLLOWED THE TECTONIC PROVINCE APPROACH DESCRIBED IN APPENDIX A 0F 10 CFR PART 100. THE APPLICANTS' PROPOSED SAFE SHUTDOWN EARTHOUAKE ACCELERA-TION LEVEL 0F 0,15G, USED TO ANCHOR A NEWMARK TYPE RESPONSE SPECTRA IS A CONSERVATIVE REPRESENTATIVE OF THE SAFE SHUTDOWN EARTHOUAKE (FOR FREQUENCIES GREATER THAN 1 Hz), COMPARING THE APPLICANTS' RESPONSE SPECTRA IS ALSO COMPARED TO R.G.1.60 AND DISCUSSED IN SECTION 3.7.1 0F THIS REPORT) . THE APPLICANTS' RESPONSE SPECTRA ROUGHLY CORRESPONDS TO A MM INTENSITY VII OCCURRING NEAR THE GRAND GULF SITE, USING THE INTENSITY ACCELERA-TION RELATIONSHIP 0F TRIFUNAC AND BRADY (1975) THE RESPONSE SPECTRA IS ANCHORED AT 0.13G FOR MM INTENSITY VII, A REGULATORY GUIDE 1,60 RESPONSE SPECTRA ANCHORED AT 0,13G IS ENVELOPED BY THE APPLICANTS' PROPOSED RESPONSE SPECTRA AT FREQUENCIES ABOVE 1 Hz.

THE DESIGN RESPONSE SPECTRA WOULD THUS ACCOMMODATE THE LARGEST HISTORICAL INTENSITY EARTil00AKE (0CTOBER 19, 1930 MM INTENSITY VI) IF SUCH AN EVENT WERE TO OCCUR IN THE IMMEDIATE VICINITY OF THE SITE, THE GROUND MOTION FROM THE LARGEST HISTORICAL MAGNI-TUDE EARTHOUAKE (NOVEMBER 5, 1983, MB=4.8) HAS BEEN ESTIMATED AS PART OF THE WATERFORD SAFETY EVALUATION REPORT (1981),

kC

' . \

~

FREQUENCY (cpe) so so so ao e e r s , a es . or as o, or os o. .

)

" N/ #'A 9NsA' mpv M 'l rc

• N , ry '/ A'W'MN w #

r ' i N A y% M ' I r c , y rfwr giyy 3m ismN y i

, \

-/YNY3 A AlY WA! / \/(NYIA A Y NA XMV \ /(W Xi A A YFAY\ 4 so

-E/XAA A AAYsV N/X AA A AA YNNN N/Y M Y\ AA Yi

~

'4

,, f/ AA(N/\A/^AWd///X/N/*AA/^A'*' W///Y/VA//VN ,,

W/X X YXX X ' sMW/X X > "X' ^ >CNMW/Xix xx X >CWJ

., ISSK/Of>dVS M2Mf/VCC(VSCMMf/VCO(Y4 < 'M ,,'

,, MDMM%3Km/MMM$dMWMMM nWR TN 3W(XXWA /\ M"'8'0"sE specmuu omnivso rnom .*

5 q

,, h(> MD'd M M / X >( 'X>M sh/fdhE'oEm"eEnE ~ " N53 ,,

K>>R>'#59mGW CxM9%Ei'SwCxM'lXX34 r x reu A AA mn.e v x r<u A# x x xa n s' 'y I N x ,re u mAAvww "

1

, -A /cNYA A YAWy A/(N vi/\ z y ww /; A /YWY A /N! YvwW ,

-N/XAA A AA X'N4 N/XAA A'M YM i NfX AA A X A x 2

/

r u//YM/'yNu mcxwxmm /'/YtXXW//XM/7VN m MME m m oESIGN x - -SPECTRUM - m,x

't. ((VV -

w/snSxsmuwcx+mmsnmwe

. mwwwwhmmmam .

g' nwn/ wow mmamxwsxxwm reux '

d bCNW / M d W X*EbN & /2K &^ OY'x^/bMAf6WG byMgm<uwcxsewow exMmW '

..CG_itM _%%.y __DMB%%W YN

_ 3_ % _ W .

~\ _/ ( N/sYA xY_N^In/\_/

\

xY _iA A!Y

'A xx _3N V \_/(N Yi mm A W i N_1Ys.i

/-

f// NAfik'bNN///X/%(\ A f mu//V'-

w/emwau/Vwawaswv,cuma x m oxmumx xx /WYWh' m a ^t'/VVR mmnu lV'VN MW -

l

.IxS$k/XMMsbMb7DNfdNMMAX?'4N'/d$64 wvsxx n xu<xxwx nwwx xwnnxowx ,

hbNiNXM M6^6M'M1/RPWXht'YpfV(R dMdd m y s e/ Rmwcammxmwer WKMMMNKi'Md.

o. o. _ o. . . . .

PERIOD (secs )

MISSISSIPPI POWER & LIGHT COMPANY SSE DESIGN SPECTRUM AND RESPONSE GRAND GULF NUCLEAR STATION SPECTRUM DERIVED FROM SSE UNITS 1 & 2 SYNTHETIC TIME HISTORY BASED FINAL SAFETY ANALYSIS REPORT ON 55 DAMPING RATIO FIGURE 3.7-f4 I

T, - L m o

i l

I I

dessw u.at's A

.O L tJ O. -

2.

. P' O M.V O 1 i

r. . ee e- 2 n no P O .I O &! TI sa

" " n E "

2 '. as 0  : 1 ". a ~ l' e  ;" " " " "

0 ": Nr "

c,,. e . .,

1

." .;;. '. :: 't  : .

.8(

- ,. - e .,.

. 4- .,,

. .r, ,

.: - - . .r. . .s, <m .. ., .

go 0 @ . c'> . Ev; 0; . ev . @ .,

C=> w

@ _ O 6. @. O O. O @

i., e @ . O. @. O. @. O e . @ 8. @ ,,, O. e .,, 6 m

e . @ e ., e. @. s. e e

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

.  ?

e . @ . O.. @. @, @ ,. O

- t

.l e @ - @ G .. 6 @, O l

e .. e e ., e ., e., e., e e a Ll.l . I .,

~X FIGURE 7 9

" , g=m 249.000',t1.1801 i -

g. - . e. .v.

cmes c,e s

y g 234.000'.fl.165' .- ,-

\

34eu 20' 6' _  : .

i e .

. : ': i '

1 249.000'

- .. - .. m g200.000'. E1.131'3 '

i ,

. v. , Of, ,,

- i

- t l . ??t.000* '

l -

See Detati at right f'or i

this ares. . -

i e

• 4.-- 5.5.W. C.T. S.

i 1 151.000' .

Structure i 1 1 3

i 1 i a i i 1 1

_2W.000' 3

i i i t*

• / ,y F 1

1 3 3 i i e' .

C i i i i g . # -

I N -

n 1 1 i #

' i a _i i n i

a 1 ) '

,j a a

a i

, M M l.l K -e i)<

i g

1 i 1

-14.000* .

1 I c

-w gyg.ggg*

\, N

. 1

. e _, -

e, .

00.m' -

)

358 "#' -

1 gp l '

= . $_ 72' 14' z

(

f0 DEL ' ~

f - DETAIL i Fig. 3 FLUSH FINITE ELEMENT MODEL OF s.S.W.CT.'B.

SHAKE / LUSH AND FLUSH MODEL MOTION INPUT AT SURFACE IN ACCORD WITH SRP SECTION 3,7,1 DATED NOVEMBER 24, 1975 (NUREG 75-087)

IDEALIZED STRUCTURE AS A PLANE STRAIN FINITE ELEMENT MODEL ELEMENT MASS DENSITY REPRESENTED AS AN AVERAGE EXISTING BETWEEN ELEMENT VERTICAL B0UNDARIES

-SHEAR MODULI CHOSEN TO RESULT IN A MATCH OF NATURAL FRE-QUENCIES WITH LUMPED MASS IDEALIZATION DID NOT USE VISCOUS DAMPERS TO SIMULATE ENERGY RADIATING.0VT OF PLANE ACCOUNTED FOR S0Il BEYOND FINITE ELEMENT B0UNDARY WITH TRANSMITTING B0UNDARY CONDITION AND VISCO-ELASTIC FORCE DISPLACEMENT RELATIONSHIPS FRS FOR BOTH SHAKE / LUSH AND FLUSH ENVELOPED

!O

me b

t utR 4

i  %*

w @* s a n 14 Qt E h b ja g - @3D'W '

64 i

e se g  :

o 8 Y o

R

~

D 'E

..o r! sh. L

.o N "O 's N e 2 2 e $3 = 4 9 .

i d d 4 d E50 d C 4

4Q

@*t

- a n */

@ e kk r

@* y@G ,

$ h;-

=2:

2: 9 + 9

• h og y S

$g, 9

[z g4 ---

$Ut 5 g g.. .

l

. IN (L

g.

-i.

i ,

c e

[ q I

4 i ' 4 h

+. - x p g

i

" , I e a t .

. 2 s s 0

I 0V

+ O tu

. V9 M. . . I ,

, m 34 .r" o

ee e ...... ..

m(

\\

~

EHS ANALYSIS 4

CONTROL MOTION INPUT AT FOUNDATION OF STRUCTURE STRUCTURAL MODEL DEVELOPED IN ACCORD WITH BC-TOP 4 S0ll STRUCTURE INTERACTION (IMPEDANCE) DETERMINED IN ACCORD WITH RICHART a HALL PROCEDURE (BC-TOP 4). THE FOUNDATION IMPEDANCE WAS ADJUSTED TO IDENTIFY A FREQUENCY SHIFT THAT ACCOMPANIES THE EFFECT OF EMBEDMENT BY A PROCEDURE BASED ON ASPEL S0ll (MATERIAL) DAMPING WAS CONSERVATIVELY NOT INCLUDED COMPOSITE DAMPING WAS OBTAINED BY THE TSAI METHOD 4

. QEncronu -

o va;w v .

i .

I i

2.0

! i.e .

l  ;'

]

1 1.6

• 8 8 '

i i

3,,

it i

1.2 -

. r 7 '

1

~

1.0 , / b -

@e .

T g[ .

J p

7 rrwins . i

.< / /~ b ,

f d tros A/  %

L N _

0 # I

.i "ILE6.LEN) ,

.... .e FREQUENCY CCPS 3 Fig.8 FLOOR RESPONSE SPECTRA EL.133. 00

_ SEISMIC LATERL_

SSE .

e

-RESPONSE-TO NRC QUESTIONS o

' QUESTION'1 DESCRIPTION OF METHOD USED-IN ANALYSIS PREVIOUSLY PROVIDED VARIATION OF KEY- ANALYSIS PARAMETERS ACCOUNTED FOR BY !15%-

PEAK BROADENING PER SRP SECTION 3,7.2 (SUBSECTION 9)

BASIS FOR CALCULATING S0Il SPRING CONSTANTS USED TO SIMULATE EMBEDMENT EFFECTS DISCUSSED PREVIOUSLY SEISMIC INPUT DISCUSSED PREVIOUSLY IN

.a RESPONSE TO NRC OUESTIONS QUESTION 2 NATURE OF QUESTION IS DIRECTED .TOWARD S0IL STRUCTURE INTERACTION (CURRENT SRP SECTION 3.7.2.11.4)

BOTH EHS 8 FEM ANALYSIS COMPLY WITH THE INTENT OF THE ABOVE SRP SECTION WITH THE FOLLOWING EXCEPTION:

THE CONTROL MOTION FOR THE FEM ANALYSIS (0NLY) WAS PLACED AT GRADE LEVEL o

MAJOR CONCLUSIONS BASIC METHODOLOGY USE FOR BOTH EHS & FEM ANALYSIS HAVE BEEN

- USED PREVIOUSLY IN THE LICENSING OF NUCLEAR POWER PLANTS THE CONTROL MOTION FOR THE. FEM WAS APPLIED AT THE GROUND SURFACE PER NUREG 75-087 I

THE NRC HAS COMPARED THE GGNS DESIGN SPECTRA WITH THAT OF m

R.G. 1.60 AND FOUND IT ACCEPTABLE L ..

, THE FRS FROM BOTH THE EHS AND FEM ANALYSIS HAS BEEN ENVELOPED FOR' EVALUATION'

[h _- - - - - - - - -

4 3

1 .

c 1:.

May'21,-1985 MEETING

SUMMARY

. DISTRIBUTION

?

d

^

Docket:No(s)?%50 4166

- NRC.PDR Local PDR

' - NSIC-

- lPEC System-

- LB~#4 r/f Attorney, OELD E. Adensam Project Manager L. Kintner

Licensing Assistant M nuncan-NRC PARTICIPANTS

.L. Kintner N. Chokshi S. Chan

't

+ -

Y .  % *

% l I...

bec: Applicant.&. Service List a-