ML20058K184

Summary of 901107 Meeting W/Util in Rockville,Md Re Steam Generator Tube Collapse Under Combined LOCA & Safe Shutdown Earthquake Loads

ML20058K184
Person / Time
Site:	Farley
Issue date:	12/04/1990
From:	Hoffman S Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 9012120315
Download: ML20058K184 (4)

Text

__,

^^

7 r

0

[#

'k

'd UNITED STATES NUCLEAR REGULATORY COMMISSIOb l N,

_j

,j.

6 WASHINGTON, D C. 20555 December 4, 1990 Docket Nos.

50-348 and 50-364 LICENSEE: Alabama Power Company FACILITY:

Joseph M. Farley Nuclear Plant, Units 1 and 2

SUBJECT:

MEETING

SUMMARY

OF NOVEMBER 7, 1990 A meeting was held with Alabama Power Company (APCO) on November 7,1990, in Rockville, Maryland, to discuss the issue of-steam generator tube collapse in the tube support plate region under combined loss-of-coolant accident (LOCA) and safe shutdown earthquake (SSE) loads. ~The issue was raised by the NRC staff during its review of APC0's July 31, 1990, amendment request to increase the-steam generator tube plugging limit for Joseph M. Farley Nuclear Plant (Farley), Unit 2. - WCAP-12659, " Alabama Power, Joseph M. Farley Unit 2, increased. Steam Generator Tube Plugging and Reduced Thermal Design Flow Licensing Report," which was submitted by APC0 in support of its amendment request. contained a discur,sion of the effects _of steam generator flow area reduction due to tube collapse under combined LOCA and'SSE loads.

The WCAP-12659 evaluation was based on a bounding analysis for Westinghouse c

-Model 51' steam generators.

APCO,.and its contractor Westinghouse, presented the methodology used to evaluate the Farley, Unit 2, steam generators for tube collapse.under combined LOCA'and'SSE-. loads. After calculating the reduction in flow area, a penalty was added to the_ calculated peak cladding temperature to account for-the flow-

-reduction;in; determining. compliance with the regulations.

Also discussed was the issue of tube integrity during collapse.

Steam-.

generators are known to have cracks in the tube support plate-region.

The staff is. concerned with the effects of' tube collapse.on the behavior of-

' existing cracks:and'the potential for leakage. APC0 and Westinghouse indicated _

that with further Farley specific analysis, tube collapse could be shown not to occur'at Farley anditube integrity would not be an isue.

LThe conclusions from:the meeting.were as follow:

1.,

APC0 will evaluate this issue further and document that steam generator tube' collapse will not occur for the 1

s i

combination of LOCA~and SSE loads.

L2.

Westinghouse will send a letter to the NRC describing its efforts-to address the tube collapse issue.

generically for all of its plants.

o

([..

'9012120315 % h 4g i

[

PDR

,, DOCK pgy P

1 1

,e

y 1

c2 contained in WCAP-12763 (Proprietary) and Handouts from the moctii-oru WCAP.127C4 (Non-proprietory), " Steam Generator Tube Collapse Considerations Presentation Materials." Pursuant to the provisionr. of 10 CFR 2.790, WCAP-12763 is being withheld from public disclosure. contains a copy of WCAP-12764. Eaclosure 2 contains a list of attendees.

Orignal signed by:

Stephen T. Hoffman, Project Manager Project Directorate 11 1 Division of Reactor Projects - I/II Off!r.e of Nuclear Re6ctor Regulation cc w/ enclosures:

See next page o,'

n UfCt

PM:P021:DRPR-

C:EHCD b

Qi 21,.

P 2

4.

.,$':4.............:..............:.............

.....;;;..... 4 4..--_:..............:

37 NAME :SHoff4;ilit...... :.... /........ _ _. :..... g.

.,:EAdensan

CChen DATE :11/27!/90

11/7t 7/90

11/GMy90 I

0FFICIAL RECORD COPY-Document Name: MEETING

SUMMARY

FARLEY A.

e i

Meeting Summary Joseph M. Farley Nuclear Plant cc:

Mr. R. P. Mcdonald P,esident Inspector Executive Vice President U.S. Nuclear Regulatory Commission Nuclear Operations P. O. Box 24 - Route 2 Alabama Power Company Columbia, Alabama 36319 P. O. Box 1295 Birmingham, Alabama 35201 Regional Administrator, Region 11 U.S. Nuclear Regulatory Commission Mr. B. L. Moore 101 Marietta Street, Suite 2900 Manager, Licensing Atlanta, Georgia 30323 Alabama Power Company

.P. O. Box 1295 Chairman Birmingham, Alabama 35201 Houston County Commission Dothan, Alabama 36301 Mr. Louis B. Long General Manager Southern Company Services, Inc.-

Claude Earl Fox, M.D.

Houston County Commission-State Health Officer P. O. Box 2625.

. State Department of Public Health Birmingham, Alabama 35202 State Office Building Montgomergy, Aiabama 36139 Mr. D. N. Morey LGeneral: Manager - Farley Nuclear _ Plant

.Mr. Janes H. Miller, III, Esq.

P. O. Box-470 Balch and Bingham

Ashford.:Alabana 3631%

P. O. Box 306 1710 Sixth Avenue North 1

Mr. J. D.. Woodward.

Birmingham, Alabama 35201 Vice-President - Nuclear:

Farley Project Mr. W. G. Hairston, III

- Alabama Power Company

Senior Vice President

P. O. Box 1295 Alabama. Power Company Birmingham,-Alabama 35201 40

Inverness Center Parkway-Post Office-Box 1295 t

Birmingham, Alabama 35201

.?

t 1

A m

as.

m

V f y, i

?

o DISTRIBUTION f acility:

Farley

[

.;tgE itk I$OEE*

NRC PDR Local.PDR T. Murley 12-G-18 F. Miraglia 12-G-18 E. Adensam 14-B-20 P.. Anderson 14-B-20 S. Hoffman 14-B-20 000 15-B-18 E. Jordan.

MNBB-3302 R. Jones K..Desai C._Cheng K. Wichman H. Conrad ACRS(phy P-315 E. Mur 10/

.B. Borchardt 17-G-21 Farley file b

Y l

I s

I l

e 1

1 4

h I

l'.

l bi

i'.

l.>

- i

'l V:

li

+

s. -

)

w.

y -

- * ^

WESTINGHOUSE CLASS 3 9

WCAP-12764

-4 i

c Steam Generator Tube Collapse Considerations Presentation Materials

.n Prepared by Gary Whiteman November 1990 s

i t

> i l

i s:

1

5, 5

.. Westinghouse Electric Corporation

'Pittsburgh, PA C

1990 Westinghouse Eiectric Corporation. All Rights Reserved i q M k.9 g 9 9 7 j$'

A meeting w;; ne'd on November 8,1990, between the Alabama Power Company, Westinghouse, and ;he NRR to discuss steam generator tube collapse considerations usir.g seismic /LOCA loading combinations.

The following tovics were discussed:

1) Analysis methodology 2)

Load combinations 3)

Effect on LOCA peak clad temperature 4)

Farl ey-speci fic - resul t s

'?

1 l'

l l

1 b

,1

+

PRESENTATION OVERVIEW f

u ANALYSIS NETHODOLOGY FOR CALCULATING P e

LOADS-l

)

DETAILED PLANT SPECIFIC ANALYSIS e

SCOPING ANALYSIS FoR FLOW AnEA e

i REcuCTION ESTIMATE i

l o

Discussion OF LIMITING LOCA CONDITION c

e L

L

. PEAK CLAD TEMPERATunE VEnsus e

max. STEAM GENERATOR LOADS e-REVIEW: 0F. PLATE: CRusN tests.

m e

CALCULATION OF.FL0w AREA REDUCTION I

ut L'

IN-LEAKAGE CONSIDERATIONS'F0LLOWING LOCA' e:

l

'I i

E i:

I a

,,.jp _

ANALYSIS METHODOLOGY FOR CALCULATING PLATE LOADS DETAILED PLANT SPECIFIC ANALYSIS p

o TSP LoAos RESULT FRoM THREE LOADING MECHANISMS

c. <.

r I

l 1

I i

t e

4 Y/(

j

-h j g _'

't }.:

i

. r a

9 I

.i!

i' e

rb..

.,.kd f

.s

ANALYSIS METHODOLOGY

\\

\\

SEISMICIANALYSIS e

OVERALL STRAM GENERATOR e

TSP /. WRAPPER / SHELL GAPS Moo a,c e

ACCELERATION TIME HISTORY LOAo r-

, a,e l_

e MAJORITY'Or STRUCTURE MooEL I

map a

e TusEs MooELEo[

a., e.

4 e

STzFFNEss MATRzeEsINTERFAc

~

i e

PLATE IMPACT FoRet TIME I

1 3

I

/

b 4

1 i

_-y 77 J

0. w.5 t

[

o 1

1r,

=.a

=

~

IM

_ e.v lll El lli Ill El lli Ill' t lli Ill'E'Ill l ll I

Il l lll I Ill

? '!

!' E t_

L TYPICAL SEISMIC MODEL MODEL F STEAM GENERATOR 4

l

i ANALYSIS METHODOLOGY LOCA RAREFACTION WAVE ANALYSIS.<

e LINEAR DYNAMIC ANALYSIS OF THREE Tust RADII L

FINITE ELEMENT N00EL CONSIDERS Tust U-BEND e

DOWN TO SECOND Tust Supp0RT PLATE BELOW

'i U-BEND PRESSURE WAVE GENERATED FROM IRANSIENT o

THERMAL-HYDRAULIC ANALYSIS

._- a,e e

e e

THREE SUPPORT CASES'RuN AT TOP SUPPORT PLAT e

TO ACC0uNT FOR Tust / TSP INTERFACE

__ a., c e

g i

e 5

1

s y

e s,,-, -- a 4

a

.a

+

f

' b 8

e a

i i

i t

WTG ROW BEAN W EL LOCA RAREFACTIM ANALYSIS 0

6 i

l y

e ww w

n-^--ee

_wy

+ - - - -

a w%

a-

--7 W-wW->-

-w m-wewr

'M r

9

b ANALYSIS METH0DOLOGY-LOCA SHAKING ANALYSIS DYNAMIC ANALYSIS USING SEISMIC MODEL e

LOADS APPLIEo-TO STEAM GENERATOR IN FORM e

OF DISPLACEMENT TzME-HIST 0erES AT SUPPORT LOCATIONS Dr$ PLACEMENT TIME HrsT0nrES OsTAINED AS.

e FOLLOWSi

_ n,c O

i l

\\

l S

7

_, - _.. _... _... -. -. _... -. _.... _. _ ~.. _.. _.. _.. _..

ANALYSIS METH0DOLOGY COMBINED PLATE LOADS 1

l e

Os7AIN MAXIMUM PLATE. LOADS F0n

~

- a,<

e COMBINE

.y.

LINEARLY CoMsINED LOCA AND SEISMIC LOADS USING SQUARE o

Root oF THE SUM oF THE SouAREs l

I O

o DISCUSSION 0FtLIMITING LOCA LOADS PEAK CLAD TEMPERATURE VERSUS MAX STEAM GENERATOR LOADS PEAK CLAD TEMPERATURE-LIMITING LOCA LOADS-e e

BREAK LOCATION - PUMP OUTLET t

RESULTING STEAM GENERATOR LOADS SMALL e-IMPACT ON FL0w AREA REDUCTION MINIMAL e

e max STEAM GENERATOR LOADS BREAK LOCATION - STEAM GENERATOR OUTLET e

i IMPACT ON PCT NOT AS SEVERE AS PUMP I

e I

QuTLET BREAx FL0w AREA REDUCTION CONCERN IS IMPACT ON PC e

i FL0w AREA REDUCTION BASED ON LOCA LOADS e

FROM LIMITING LOCA POR PCT l

e TSP LOADS REDUCE TO SErSMIC LOADS ONLY l

l 9

e..

m

.x

.ama,

.a.aama e,.mmA e

a u_.u_m,awa 4a..auar.,m_.

+.e2.___r4_-..aaa 4 - _.

s,

,__m__.a...

m

,,aa

__,m

-m_--

o

\\

1 jet

.\\

's

_ a..,

m.-

' dl

\\

'4l 8

s I

st 3

, k ej,4 r

y W

1 lf :

y e

l!

t eM i

u 1

e

.y

,.' e h

t 8

i O

y 1

d g.

i i

t L

I 8

e *1

t f

_t s

4 0

i@^

@m y

\\

3 i

I Y

9

y t

Ih lg, 4

1

,/

v I

C J i

e e

.e s

8 4

n a,

'I i

@ ' o gi

)s.

e-L

(,

• r

.. ).

e a

}

3 y

e e.

\\

f

~7 10

m..

as

.w-mya ms

,se, w

p-a 7

aig

.Aww i7--

---

e

---

w

.----------i---------w--

e e

e i

e i

py

.-.w e :

(TM/s.rix om y)

~

n.

6 81 2

i G

s t

/

/

• 't j

i /

g k

M Isae er i

[ y..

~ ~

a e, /y

/

\\

x/

y s,n a

w

,/ '

Wh+.

M a

f/NT MW

,1 V8 k$'

l SttTsou 9.m3e*

r 11 l.

-__._,__..a

_w

=

REVIEW 0F PLATE CRUSH TESTS y

e Two TasT PaosRANs ROUND AND OuATREFOIL' Holes e

UTILIza SIMILAn TasT-SsT-Up AND Pnoctount e

a., c e

e e

- a,c.

e MEAsunt 1A;C Post-Tast MEASUREMENTS e

CHANGE IN Tust/Hota Caoss-SsCTIoM e

Daystop RaLATIONsHIP sETWEEN PLATE LOAO AND e

Loss IN FLOW AREA ACCOUNTING FOR CoLLAPstD Tusts DUt To Post-ACCIDENT SECONDARY-TO-PRIMARY Passsuna Daop 1

12

aa.aas

--+-

e.x..

.y

+

a-m.,

-a

-~

a 4

8 e

e e

a j $

PLATE CRUSN VEST SET-UP 13

e n'.

e.

.zy -

Wi

~

-l DISTORTED PLATE GEONETRY -

~

l 1"

L..

CALCULATION OF FLOW AREA REDUCTION 0., e O

CALCULATE 0

ASSUME

~

" A,C (TYPICALLY 6, 8, On 12-WEDGE'Gn0UPS l0CATED SYW4ETRICALLY AROUND PLATE CIRCUMFERENCE)

O CALCULATE

~ " ' '

0 CALCULATE Ass 0CIATr.o FL0w AREA REDUCTION-0

_ CALCULATE TOTAL FLOW AREA REDUCTION SY

- a.,c h

1 M

e 5

ANALYSIS METHODOLOGY FOR SCOP FLOW AREA REDUCTION' ESTIMATE' UTILIZE EXISTING DETAILED ANAL o

COMPARE KEY PARAMETERS FRoM SE o

r-

,a,c.

o j

0 1._

o COMPARE DEVEtoP[

o

~ * ' '

ESTIMATE Flow AREA REDUCTION o

s

,c

a. c APPLY FACTOR,

Fon ANALYSIS UNCERTAINTIES o

16

I u

FLOW AREA REDUCTION RESULTS FOR FARLEY

]9(Hoost D) UsEo As A 'B e

DETAztso ANALYsrs NAs Nor BEEN P e

RFORMao FOR Serres 51 STsAM GENERATORS 1

l l

COMPARrs0N OF KEY SarsMrc PARAMETERS e

- dt., c e

e COMPARE SsRras 51/ Hoort D StzFFusss RATIO =

' o, c a

e m

17

FLOW AREA REDUCTION RESU I

e DEVELOP L YIELDPOINT[

e J

]a.c e

TWO METHODsPLATE INELAST a.,c i_.

a ESTIMATE FLOW AREA REDU,CTION e

...c J

NuMsERorCOLLAPSEDTusES_j SERIES 51 1.

e FARLEY

<1 (AS%4E 5 F0a CONSERVATISM e

CORRESPOND

• Y0 TUSES-DIR Flow AREA REDUCTION PER WEDGE SERIES 51 -[-

]* Ac

)

e FARLEY - 0,15 %

e i

FLOW AREA REDUCTION PER STEAM i

SERIES 51 -[

]'Ac e

e FARLEY - 0.44 %

I

\\

IB 1

.-3-,

,--s

..ww, v.

...=v.

.-.-e--

+ + --

.._.,..-e.

r

---..--,+---m-.

1 FLOW AREA REDUCTION RESULTS'FOR FARLEY (CONT'D A,C APPLY FAcTon or ron ANALYSIS UNCERTAINTIES FLOW AREA REDUCTION REsuLTs e

SERIES 51

.~

' " ' ' ^

e FAnLEY - 0. 8 % on.<1.0 % ~

I l

j l

l l

19

i 1

I i!

)

}

I1 1 e i

.t.

19 O $4eid! 21 l

4 8AALf?

-l'.

1

. [j

/

~

l

. !'; i i

Il Y

l s

l l

I i

ll g

I l

j l

I !]

l

)

I l

I 1

I e

l

\\.

i 1-

,I

\\

1

l. -

I i

\\

I, ii!h I

1 8

\\

L 1 j l ),9 l

L mr

.\\

l1; I

i l

r

\\

' a,i4

)i j

{

h

\\\\

o

<\\

l

. t '4 i

s

/

y 1

. \\

8""4 e,.

v =

-a

~

80

ISE N.

., j its 78t M W 9

• 4 tit 7p

(

SEISMIC SPECTRA COMPARIS0N 20 1

,...., ~,,

TUsE COLLAPSE. CONSIDERATIONS-WCAP-9659 LOCA IN-LEAKAGE ROUND OR OvALIzED TuarS IN-LEAKAGE IS LESS THAN NORMAL OPERATION 4

LEAKAGE PRESSURE DIFFERENTIAL IS'LESS THAN NORMAL PRIMARY TO SECONDARY AP SECONDARY TO PRIMARY A P CAUSES LESS LEAKAGE THAN PMIMARY TO SECONDARY A P OF SAME MAGNITUDE THE PRESENCE OF'A SUPPORT PLATE i

(COLLAR) REDUCES LEAKAGE:

i 1

i 21 L

. ~.

aaa..mm-,ww a

no ---

w

..s,-ea erm an.a:.,su-us,s e

.a a en a. -

p ees 2

a--e a

r

cA. jb, c.

t

?

l l

l FIGURE 18.

O!WLED Tutts WITH FAT! Gut CRAC M

l l

22

ak a

a sMma3-er a,--*a a-w.,-s as

.u -en-m--'

-a

+-

mem-a-Aa A-a-enseen

, oms,a

--m-4e-*M-+a sedd-A--

Ja a-a.msa-.e.r

ass -

-s e

assea s

e~=A A- - -

8 4

0 0

8 d

h 0

I M

V EC 6

E i

G-

=

M C

6 een G

Y C

E

55

5 b

l I'

t l

c E

ase=

w auas G

w

.b.

b l

I

(

23

_-u-_

A e

um-es-a+.m-._a a

_h_

=

_.p_m am._

_._e.

___u-%

A,h4s_s.

4 wJ,.es

,__a

,s.s a

4 ana A

s_..

e e

g 4

9 0

h, t

\\

l I

l i

q l

9 e

l eW

=

4.J

&if

$ne w

2 m

he eh N

O

.D t

1 l

5.

W

>=

E 5

e su.

l h

(

24

)

__.en

wm_,

ama m.

o-

_m4

%w&4_A.aa.

m.

a, w

4.a.,

_m.._

a a

p-.

s 1

e i

I O.,

b y

4 a

l l

1 v

8

-O auJ E

3

%*n N

e C

em.

2 1

I 5

w p

8-N w

i I

i 25

'+wwe*%

4, sed.

mm.-

--s

.a e

a m---

e O

e

- t 9

i 4

8 I

M PM 97am M

is=

w e5m 8

S C

3 s

m E

26 0

i Tust COLLAPSE CONSIDERATIONS WCAP-8429 COLLAPSE CAPABILITY RoUND TustS WITH THROUGH WALL EDM StoTS

,a s,c COLLAPSE PRESSURES EXCEED e

a EVEN WITH 10 PARALLEL 1.5 INCH THROUGH WALL SLOTS WITH PART THROUGH WALL EDM St0rs COLLAPSE PRESSURES EXCEED

_,y e

FOR PARTIAL PENETRATIONS EXCEEDING 1.25 INCH-LENGTHS I

27

ye...=

o

-ana-nsas.a

.a-.saene am ss.a.-

s-r<

a

-me-a s a

~m s-

-~ a

--aa-a-

- -~

ea i

l e

' 1 i

TA8LE 51 Tutt COLLAPSE TESTS (PART ANO THROUGH WALL FLAWS)-

a

[

28 1

-~

_4aJa

_4, Ag, e

,.ma mm.--..m ca.

E'.s-a-

-e M..mahweme.a.a.--

,a e.m.ia esa b.*e--si a

, eda 4-

--.+.

m-mi.J

-ww.ei.J.T---

-p_d.se e..

eea 4

4 g

r 2

1 O

[

gW M

W c

eh g

5 ".

e s

m

, ga g

h8 j

5 88 m

E

@E

.w hI

=

W ws g

5j s

w 1-

~

5 i

\\

L 8

'x 2

4=

3 r

l e c, W

3 w

4 g

di b-I A

' S a

s l

p N

E 4

N z

.w r

jI I

g-k

- =

a typ

=

J 3

[

~~g I

3,

'g E

i i

w

• O

=

i 5

2 W h) t 5

l d

8 N o

i 2

{

, d-e 3 -_.

P

'k y

8

-';;L g

O m

n l

-. - -.. ~....

.. - -. -.. ~ -... _, _,.,...........

..-.A 8

TusE COLLAPSE CONSIDERATIONS WCAP-8429.

COLLAPSE CAPABILITY OVALIZED TusES j

PARTIAL PENETRATION EDM SLITS IN TUBES OVALIZED

- i a,s,c.

TO,

HAVE LITTLE EFFECT ON~ COLLAPSE-PRESSURE.

e 30

4 e

8 g

=

,1 5-I 68 5 a3 e

i 5

h.

b s

I Ji hk i

3

{=,=

^c k

a N*

3 5

b v

=

j[

g-m

=I

\\x s

g k

(

=

s e

i

$>I i

i u.%

~

3 i

31 i

4 I

t TABLE 510 STRAIGHT OVAL PULL WALL Tutt$ COLLAPSE DATA t=0.043".{

} *, e, c.

'h Y

4 g i

i I

N 32 l

'W i

I E*

a 1

l C4, b, c.

I 1

l l

i 1

1 d

l l

N ff nom'0 3$',,

8gt Mirad Tubes IA l

33

t.

l Tust COLLAPSE CONSIoERATIONS

\\

WCAP-8429 i

j COLLAPSE CAPABILITY DENTED IUSES l

e PLATE DEFORMATION UPON CONT CAUSES TURE OVALIZATION AND REDUCE COLLAPSE PRESSURE VS ROUND TURES PRESENCE OF PLATE ENHANCES CO o

OF OVALIZED TURES COLLAPSE PRESSURES WITH COLLA e

LOAD WITH DIAMETRAL DEFORMATION E r-1

,5, c.

- A b, <:

M 3

l 34 I

r

t.

1 i

a I

TASLE 512 DENTED Tutt8 MECHANICAL TEST PLAN A,4 i l

t t

ilmens N

i l

35

i TASLE 512 (Con't.)

\\

4 4

DENTED TUSES MECHANICAL TEST PLAN o,c 1

0 36

-.~._

~2

--,.s...

~a-

_n--..

u s

a

.,7-i j

e e

1 TASLE S.13 DENTED TUSES MECHANICAL TEST RESULTS m

l $

i 4

l l

i sames e

N 1

1 f

i I

37

i P.

i i

4 4

I l

cA., C 1

)

i 1

l l

Figure 537 Effect of Denting on Collapse Pressure 38 i

,e-

-e 7

-,a-+.-,.

w-,

~~

~-.-,e,---

0.

1 TUBE COLLAPSE CONSIDERATIONS 4

l LOCA IN-LEAKAGE MULTIPLE AND LONG THROUGH WALL CRACKS 00 NOT LOW)

COLLAPSE CAPABILITIES TO MARGINAL LEVELS (HIGH CAPABILITY)

WITHOUT COLLAPS'd SECONDARY TO PRIMARY PRESSURE FOLLOWING LOCA RESuLTS IN LOWER LEAKAGE TNAN DURING NORMAL OPERATION 1

THE PRESENCE OF PARTIAL PENETRATION CRACKS DO N SIGNIFICANTLY AFFICT COLLAPSE PRESSURES SIGNIFICANT CRACK EXTENSION OR PENETRATION IS NOT EXPECTED TO OCCUR AS A RESULT OF TUSE COLLAPSE 1

j TO CREATE THE POTENTIAL FOR TUBE COLLAPSE 39 i

t..

Tust COLLAPSE CONSIDERATIONS FARLEY 2 LOCA IN-LEAKAGE IN-LEAKAGE IS EXPECTED TO BE LESS THAN NORMAL OPERATION 1

LEAKAGE IN THE POSTULATED EVENT OF A LOCA 0

PLATE DEFORMATION IS EXPECTED TO BE LESS THAN i

THAT REQUIRED TO INDUCE TUBE COLLAPSE

~

- a,s,c.

0 Tust LEAKAGE IS REDUCED IF COLLAPSE DOES i

NOT OCCUR a,e,c.

'~

}

g

~

i l

40

i!

d l

. oo ENCLOSURE 2 NOVEMBER _7, 1990 FARELY STEAM GENERATOR _ COLLAPSE MEETING ATTE_DE_ES N

NAME ORGANIZATION Steve Hoffman NRC/NRR/DRP Brad Moore Alabama Power Company Kulin D. Desai flRC/NRR/SRXB Tom Timens

-Westinghouse Nuclear Safety John Houtman Westinghouse NSD/SM C. Y. Cheng NRC/DET/EMCB H. F. Conrad NRC/DET/EMCB Jack Woodard Alabama Power Company A. Alapour Southern Company Services Dan Malinowski Westinghouse NSD Gary Whiteman Westinghouse NATD Clem Eiche1dinger Westinghouse DCPD Rick Mullins Alabama Power Company Richard J. Morrison Westinghouse NATD Tom Pitterle Westinghouse NSD Emett Murphy NRC/DET/EMCB Keith Wichman NRR/DET/EMCB Elinor Adensam NRC/NRR/DRP