ML19322E178

Summary of 800205 Meeting W/Pwr Pipe Crack Study Group in Washington,Dc Re Progress & Schedule of Study Group Effort

ML19322E178
Person / Time
Issue date:	03/07/1980
From:	Shao L Office of Nuclear Reactor Regulation
To:	Eisenhut D Office of Nuclear Reactor Regulation
References
NUDOCS 8003260233
Download: ML19322E178 (14)

Text

.ym T7M

• M UNITED STATES y ) jfi NUCLEAR REGULATORY COMMISSION

r. l WASHINGTON, D. C. 20555

\\.

MAR 7 1980 MEMORANDUM FOR:

D. G. Eisenhut, Acting Director Div?sion of Operating Reactors FROM:

L. C. Shao, Chairman PWR Pipe Crack Stuc'y Group

SUMMARY

OF MEETING 0F THE PWR PIPE CRACK STUDY GROUP ON FEBRUARY 5,1980 The PWR Pipe Crack Study Group met on February 5,1980 to of: cuss the progress and schedule of the study group effort. The meeting agenda is enclosed and a summary of the major areas is provided below.

The first area discussed by the group was the collection of foreign experience data.

Lawrence 1.ivermore Laboratories (LLL) has been contracted to assist the study group in obtaining.and assembling foreign experience data.

The initial effort in obtaining this information will be by a combination of questionnaire and telephone calls.

The second area discussed by the group was the progress of each of the subtask efforts, see attached agenda.

Tables listing all of the domestic PWR pipe cracking experience were provided by subtask group 1.

These tables will be integrated with a table of vital systems, developed by subtask group 2, to establish a priority for evaluating the safety consequences of cracking ~ in -~

PWR plants.

Significant discussion was generated in the meeting about whether to include water hammer loads in the mechanistic evaluation of cracking.

Concerns about including water hammer loads arose from the fact that these loads are difficult to quantify and that currently a staff program (task A-1) studying these loads is in progress. A decision was made by the group to include these loads, if definable, in the mechanistic evaluation of syc+~ns where historically these loads have occurred.

If necessary additional ark in the area will be recom-mended for the long term program.

The remaining subtask, groups reported that their efforts were progressing within the target schedules and that no major problems have been encountered.

The next PCSG meeting to review progress of the subtasks efforts is scheduled for March 5,1980.

f Larry C. Shao, Chairman PWR Pipe Crack Study Group cc:

See attached list 8003260 M3

D.'G. Eisenhut itAR 7 1S80 H. Denton R. Minoque S. Levine V. Stello E. Case G. Arlotto F. Schroeder T. Murley N. Moseley L. Shao S. Hanauer S. Bush W. Hazelton A. Taboada J. Muscara C. Cheng R. Gamble R. Woodruff V. Noonan R. Bosnak J. Burns T. Marsh

'l V. Pancieria J. R. Buchanan TERA OI&E(3)

R. Fraley, ACRS NRC PDR a

t s

J 4

A E

l

---

e-------4.

+-~ - - -----

'~---

' - ~ ~ " " ' ~ *

~

O

/

4 AGENDA I.

Introduction II. Foriegn Experience Review Status III. Sub-Task Group Status Sub-Task 1 - Defining the Cracking Mechanism - W. Hazelton Sub-Task 2 - Significance of Cracking - V. Panciera Sub-Task 3 - Determination Cause of Cracking - R. Gamble Sub-Task 4 - ISI and Leak Detection - C. Cheng Sub-Task 5 - Review ongoing Programs and Recommended New Programs - J. Muscara Sub-Task 6 - Report Organization - S. Bush IV. Technical Discussion V.

Sumr.ary c=s:3

/

.ra:,

l bl

~

I

\\

I I

I i

i n

.', -... g-I t:

2

_.n

- s es L.

a

g. _. _.

u 41 E

t S

i t

l n

w -

4 L

?

e g

t g

3 h

+

Iq 6

b 4

e e

Te X

2 DJ t

2 i

y a

d e

1 v

• 1

~~ !

.i J.

2 f

L.

\\

3

.2 7n'

.i s m-

-b h.~

50b $ 25 31 h.gljea-u

T-:-i l ;4 i>

-j lpi ih.:

upp c2-

,. p p==d 4 o.j.g t,/ 5 l $

. :2 fidd f% 44o6 4h 345 Ed 1

i ineil i

i

l 2:

_ l

---...q.

...... i m,,

If f "'"

N ' bll

$f lll;') h l,

~

[

4m.

0

.9 d.

s e

't l

• * " * ~ * * * * -

• • bn E

a f

3 se 3 E 4

e_

.I,

. ~-

Wl

-p 8

i

?

e 9.-

z1 l

b 5

q y

b b

- ~ -

3 h

~

~

f tfe i

X 2

b 1

3 3

x 5

2

~

.s I

v 4.

i9

'~*

l

~l

.i 2

'l f

9 s

. 1

.J e

E<R. -}b E

T.

e u 2;.9 n

"*df l 5'8,

.,f f 't

_N

[

d-4 d, i

-3. J b_

el.-i jjhf ja

-j

,o i a

s

'I127:5r) 4

=

.J 3 r

i

.o g_'

.i y4.i t jn.j

'. gy l

.i 1

,=

.. p; *.

2

>3 t,

a 42

.iw l

ll uddlidd :

g o

345csd f% Jdet am/ s i

j i

l il i :

ritil i

i l

l

i I

d i

.k(! ij(!.Rhi&. - GMli!ddjil4 a,

i j

.g.

}

i i

i I

I

!ji I

'u l

l._

l 6.W I

I I.

l

.sy 3!

-l l

t il 1

!, d,.._. l 3

v a ll -

I l

o

'sl l

1 g

il if 3gg.

l 1: 11 1

311

.I I

o

'l l

!J d.

/

t I

f ill 1

E.11

."1 k

-jj] liiiIil1121iiii.' '. ' " " ; " >

i.

a 5..si'

. __ _ I I

d Tk

$v li

{

_v->J1rd! #

r ch I14 2

a J4 2+s.. r.

,d a

11 - 1 u

I.m.

m:; 1..m c. Jag :. 3 ;nd.

2 4

s o,a a e;

B I

y 1

i 5I t

ti a l hih b{ha i

l

{'

t._

t

' Fi i

I lp l

g

-1 1

n 1y.

1;

!.11 i

g X....

., l! '

l

, wg.._. ;

1

,,,.Y

,3 il 1

1: 11 j, g; 1:ll t l-

-- I i

. 11 i

i,;.._.;

9il sd ej

• k i

I 1:11l I,;

-l

,81 l

-53 1;ja; ;"; qui asyt gh) if n a as a it l,, n &p2, 1 31llhf[ ffdi. 7 44 wg. um u e !!! Sui JI lh i ! 3 AL: ~' 4

a e s sinWlY OF PWI P!PE CRACKING EzCuesse 5.6. F swarta Nazna Caacas DESCPIPflon l PR05A3if CAusE PUulf SYSTE.'t NO. P!PE $1ZE I ms a-I ane.sn Ceaus

asne, 2

I vts wie e2 ? iaCC tieeie see wt. s I. vts mis e2

• uaeste-aos

== s i no wie sue e.o se mise 6 neceu.e. wiseie ia.e sn.tre we e maie 1 N0 wie meep No ' vibraties Artenses I CTC) I e ee eispie mie m,eue Cesia.t e.cire. 3 e wat w areinisee mie vinnue (CCs ~ l see.ee votier i tCCs t l e seat n orsie um mia viwete. crrmies e i Co.ui.e. sere, t ets wie 2 isscC sein==Iowse Cei.en Citres t Cxs e i e viwane. asuur Coins Ci e. a [ win een w vincati. e l Cei.enCures2i Cv.Cs esies nee.e own. s =0 no stm . Ca ient ani=. 3 .0 s.eii r. .ieei..ies n ne. t <CCs i i e nie er orsi. use wie seat neren.e seaueCasiusciman 1 3 e .ee ewei vipecie. 9 C. Caos b4 2 40 eeles near Pumpe Or sei.es viersties ers 'x e recier i aCCs i e nielavatseores. u.e mesue. st. Cel8uhen I CvC3 2 e seies meer 9wes

1. itratte Coisat anin.

i e s.eii r one minie nies etwen.n .eee ina Cxs 2 40 eeies mee

• wee uwsu.

m. 4. Assiesen 2 to.en lesection I

i et$ eele 42 ipHietereinee r.eeise so.t i Cave. ani,. i e s.en r e.e.ieeie.ies n.nties !rdian point 2 CYC1 3 40 esies mese # wee vit-etten ens 3 en seies meer Pumos er sei.es vieretion Coat. ineet sese.e i 40 sele WeePwe titeettes !aeise Peist 3 C*ee volwe Centesi i TC$ seie toesteresa.e CTC3 1 e wie meer Pwo vieretien someonee I CVCS I 40 moles neer ewes vitration see<ter Caeleet Ciesewe i 40 moles meer Pwes siteetten e y vis sole IE5CC 491istaae g l usese see oeste ECCS g a seat w Oreis Ltee wie vinceties Marta ames t CvC5 I 40 usie toer *ume vibraties 4 asiastee. Seeply I 40 testrureat Line sete miseeatietoe assaoe 2 (CCS i 10 veat er Drain Liee meid vibratian base 3 touter Care Isefeties Coeling e I e Secole Line unie vttestion Felissees I j CVCS i e "eis eeer Pwe titration Caeleet Ascirt. 2 ac

• ;il v er Heele tseie vitretten g

^ esvrs s, iwo e,.ei.e . t ero ne. ,re., e asi i ers i o e e t s.un i Cais e amiet. =0 s en t se eisele soie n ecatise e Ps'at teecn 2 CvC1 l 1 mole toer Pee titretion

• fett infocuea i

vCg este iG5CC E.E. Giana l .e CvC3 3 90 esies kee swee vieretion Seies I r.eelaat estice, i 10 8' Smell T se gisele miss viereties CVC$ l 40 mei 9eer Pwe siteet+en .ea -, i C.aus. eat se,s, i .n seie.e

r. SCC Ceei44: e ort.

I to 1 meli i se steele inere vieraties s ser.,, Cxs i e .ie m,yes

ttweli.e

.ua 0. ta, mun.,, (, i* h [ar%I{i {h II. O K b x jg l\\. dw; d ' Lo

s SUfW.RY OF PWR PIPE CRACKING ExCLuSiHG S.G. FEEDHATER N0ZZLE ERACKS PLWT SYSTEli N0. PIPE SIZE DESCRIPTION PROBABLE CAUSE LERS 11 " Surry 2 Containment Spray 1 YES Weld ilAZ IGSCC Three Mlle Island 1 RifR 1 NO Weld Near Pump or Valve Vibration Condensate F.W. 1 NO Socket Weld Vibra tion Coolant Recirc. 1 NO Small T or Nipple Weld Vibration Containment Spray 1 YES Weld HAZ IGSCC Spent Fuel Fool 1 NO Weld itAZ IGSCC Three Mlle Island 2 RilR 1 NO Weld Near Pump or Valve Vibration Trojan 1 Reactor Coolant Cleanup 2 NO Welds Near Pumps Vibration Turkey Pt. 3 CVCS 1 NO Weld Near Pump Vibration Other Eng. Safety Feat. 1 NO Drainline Weld Vibra tion Turkey Pt. 4 CVCS 3 NO Weld Near Pump Vibration Yankee Rowe CVCS 4 NO Weld Near Pump Vibration Reactor Coolant Cleanup 1 NO Weld Hear Pump Vibra tion Zion 1 CVCS 1 NO Held Near Pump Vibration Zion 2 CVCS 1 NO Weld Near Pump Vibration BASED ON LER'S TitROUGI SEPT. *19 i

i SYSTEM

SUMMARY

SMALL (<4") PWR PIPE CRACKS LERS THROUGH 9/79 J SYSTEM PLANTS l.ER ' LEAKAGE CRACK PROBABLE CITATIONS LOCATION CAUSE Arkansas #2 1 YES Calvert Cliffs #1 4 YES MOST FATIGUE Calvert Cliffs #2 S YES CRACKS CAUSED FMdt.in Neck 2 YES IN WELDS BY Ft. Calhoun #1 2 YES LOCATED VIBRATION Ind. Pt. #2 3 YES NEAR Ind. Pt. #3 1 YES PUt1PS CVCS Kewaunee #1 2 YES No. Anna #1 1 YES Palisades #1 1 YES Pt. Beach #2 1 YES R. E. Ginna #1 3 YES Salem #1 1 YES Surry #1 1 YES Turkey Pt. #3 1 YES Turkey Pt. #4 3 YES Yankee Rowe 4 YES Zion il 1 YES Zion #2 1 YES Arkansas #2 1 YES Calvert Cliffs #2 3 YES IN WELDS VIBRATION Ft. Calhoun il 1 YES AT SMALL COOLANT Palisades #1 2 YES "T's" AND RECIRC. Pt. Beach #2 1 YES NIPPLES Salem #1 1 YES ETC* TMI fl 1 YES ~~ . Indian Pt. #1 1 YES San Onofre #1 1 YES $3T ok 1 2 Y yE RHR -Ind. Pt. #2 '3 YES NEAR PUMPS Prairie Is. #1 .1 YES OR VALVES TMI #2 1 YES TMI il 1 YES Cal. Cliffs #1 3 YES MOST CRACKS FATIGUE REACTOR Cal. Cliffs #2 3 YES IN WELOS CAUSED COOLANT Kewaunee #1 1 YES IN LINES BY CLEAN-UP Trojan #1 1 YES LOCATED VIBRATION Yankee Rowe 1 YES NEAR PUMPS Trojan #1 1 YES MOST CRACKS VIBRATICN Be r a ey fl Y ELDS ECCS Cal. Cliffs #2 1 YES OF YENT Farley il 1 YES OR DMM Millstone 42 1 YES LINES Oconee #2 1 YES MAIN STEAM No. Anna #1 1 YES CRACKS IN NOT SUPPLY WELD IN DETERMINED INSTRUMENT LINES CONDENSATE TMI #1 1 YES CRACK IN VISRATION FEEDWATER SOCKET WELD 9

SYSTEM

SUMMARY

SMALL K4 ) PWR PIPE CRACKS LERS THROUGH 9/79 SYSTEM PLANTS GR LEAXAGE CRACX PROBABLE CITATIONS LOCATION CAUSE 6 OTHER ENG'O TUR' KEY PT. f3 1 YES CRACK IN VIBRATION SAFETY FEATURES DRAIN LINE WELD REACTOR' CORE Oconee #3 1 YES CRACK IN ISOLATION WELD IN VIBRATION COOLING SAMPLE LINE. SPENT FUEL Arkansas il 2 YES IN WELDS NOT POOL DETERMINED TMI fl 1 YES HAZ IGSCC CONTAINMENT Thdian Pt. f2 1 YES VENT TO VIBRATION HEAT REMOVAL PUMP WELD ..a h 6 .--.--mm, w w

.... ~ -.. - -... - ~. ~.... s e s SulTERT GF BR SAFE-EM AM PIPE CRACK!M PtMT SYsiu No. PIPE

f5fERIAl, DETECTION DESCRIPTION LDS

$!ZE "ETHW) I 6* UT l v154 Ano ET InLIT P1Pt ggg en Poggf :ygreCY Cisgeest I f 6 Is.,v54tts 3 'stCIst sv.P455 1 4* 30s of utta mAZ M 2 20* Capecu 17ttL v!5uAL suction PLPt a(La mAZ (C*$ 1 10' 304 UT stLDta (L30m LtAs Confalmqui titgitat (gut t C00 Pts I atCISCULETIan I 4* 300 Pt atCtaCIA.ATION E!MS att:aC SAFt-te i 10' 304 Pt 0.0. InstCAflant is n0ZZLt M Sart tte TO apt 1 2* 304 vi5ual telfewgef List 5t GA150tB 3 . SECIRC STJA55 9 4' & 6' 304 vl5wAL. PT. St. UT AEAC?00 ditt CLEANWP S 4' & 4* 304 V!5uaL. LIAE. UT PT = DDelatAALIIts SuPPLT I 4* 308 Ut = etACTOR Cost !$0LAT104 C00 Lins 1 3* 308 av0A0 Cat 10tm 3 'etClaC 87 PA55 3 a* 304 Los dLO ECCS 1 10' 300 ttAE. Pf. UT C0st 3PRAf 5 Art 120 1 10* 304 LIAt IGSCC atAC'OR CO#t 150LAf!04 C00Liut 5 Art-1 14' 30s Ilt fuanact Sta51YtIta ta0 atACTOR CCAt 150LAf!04 C00LiuG Saft. I 14* = Ut FUth4CE 5t45tf1710 00 UT. FutaACE StW51TIIto C10 RETuMI SAFt-tm0 1 CatlM4 3 FEEDS 471R l 3 6* j. LDE l 304 Uf = t tto st*DRA SArt HO l 1 OLAnt Asq0LO stCIRC tvda55 5 8* 304 Uf dLa stAC70% ditt CLEAN-UP 1 4* 304 TISUAL. t!T etLa mal I5 Aft-t40 Af a#1 f 10* !EC*ith VISLAL. df. #f 9 9Cl2LE *O SAFE-t40 CRACS Otvict IESCC I l UT AAG #7 (1 aAfC41 i REC 1RC tv-PAS $ l 1 g 4* 304 f the l 1 l 20* 111CIL ] PT l vlluaL I htLa nAl i 1 l 4' ':!PAft!CE I lM LA CBC511 l f tfahAftt n0Z Lt 5AF(-140 1 l 4* l 304 1 LDs AND vl5uaL g IG5CC -- MILLSTN 1 ' atC aC tv Pa55 3 2' 8 a* 30s st5unL ANO 97 = 848 1 6' to 2* 30s LEAS its? WT A40 (DE etta MA2 4 atAC'On dAfta CLEAs-up 1 dl8 30s

• 09ftCELLO

, atC:aC sf.Pa$s t i 4* f Jos i Uf l PIPE EL30u

• tht witt 70!vf, ICCS

( 1 4* 304 UT SArt 00 70 PtPt IE5CC l tCCS l 1 4* 304 VISUAL C9CUNFttttf!4L !G5CC I 2 a* 6 4* 304 115uAL

• DT RCn (Int a PIPt stmo j 8tACros uAftB CLEAs-up atAC?og C0tt 150LAfl0R COOLING l

t 4* 304 PT P!Pt st40 TO 5 Aft-00 075fts CATER 1 CR0 attuas 1 3* 31 6

• mv0a0 5fts fust l SPAssit visa.AL Coat $PtAf 1

C#9 1 304

Lpt l 5fL'8 ftet SAft-00 af RPt 1

= 304 i PT IG5CC F~4n4Cf 5Faltt;;ta 'fII* to 10* i CAa904 57tti , UT (L30u 14 3 PRAY D178

• DC= toff 0N 2 (CC5 3

M i PLACw SQ"CM 3 atCIRC SMa$$ 2 a* 30s ' Uf. PT. Aan af ? (CC5 2 12" te 10* CA800R 5*tIL . UT. af stLO mat i God P!LG214 % ttAC708 eAftt CLEJbdP 1 t (* 304

• T!5LAL htLa bl.0 CITIE51 4tC:st ev.sa55 2

5 e* 30s vIluAL. wt 7 A0 CIfitt 2 EECIRC af.Pa55 2 l 4* 308 uf dia ALACTCt matta CLua-vP 1 s' 30s visual w(LO 9 T AuS in 4 Ag0 $ LOOPS eteq0nf TAe El 1 (CC5 i 4* 304 97 L 575I0 On Lgt5 twoouGN SEPf' 79 l e O? O ~ l ~ A o kX ~ \\

Table 1 - Summary of PWR Feedwater Piping Cracks Pl. ANT EXTEllT OF CRACKING (NO7.7.LR VICINITY) PIPING COMPONENT _ PROBABLE CAUSE COMMENTS Max. Location max. t;>. of Linen Depth Depth Crack Cracked Wentli@ nunn D. C. Conk 1/2 Thru wall kOP 8 of 8 elbow Corrosion Assisted 2 cracks thru wall Fatigue licaver Valley 0.400" 9 0' clock 3 of 3 elbow Corrosion Ausiuted 13 additional fab.. relate Fatigue indications repaired Knwaunce 0.050" 7 0' clock 2 of 2 pipe Corrosion Assistd 3" dia, aux, feed near Fatigue SG inlet l' t. Hench 1/2 0.047" 3 0' clock 2 of 2 reducer Corrouion Ausisted 3" dia. aux.i feed near Fatigue SC inlet li.n. Robinson 2 0.750" 9 0' clock 3 of 3 reducer Corrosion Assisted Shallow cracking in nozzi Fatigue under thermal sleeve Saled 1 0.235" 4 of 4 elbow Corrosion Assisted reducer Fatigue San Onofre 1 0.100" lower half 3 of 3 reducer Stress AscIsted Multiple branched cracks of reducer Corrosion evidence of some fatigue Surry 1/2 0.080" 2 and 5 6 of 6 reducer Corrosion Assisted O' clock FatiRue Cinna 0.107" 8_:30 0' clock 2 of 2 elbow Stress Assisted Cracks also at deep Corrosion / Corrosion machining marks Fatigue i . Zion 1/2 0.088" 4 0' clock 8 of 8 elbow pipe Corrosion Assisted Fatigue j l

d l O rwl a t t an o oz si S l r ao T h N d E nf M uo M o O f y C t sig k nn S cii acp rii Cvp E d S e U t A s C is E d s L o A l z lA y n ll l o o a l o R n ou P a og ri t rt o oa N CF TNE NO PM O e e C p p i i G p p N T 2 P T P I a o kcn s r ) e C Y n T

i. d 2

2 g I I e n N k f f i I f c o o p C on i I r 2 2 P V .C o aL r E. N e I k t Z c n Z o w 0 x l d N ak c c ( mc k '0 o a c F G nr o N oC l 9 R I i c W K th d 'o P C at n A cp a f R oc 2 o C LD 1 3 y F r O nn T un N u E g "0 S T .h n 0 X t i 5 7 E xp r 1 2 ne e 1 HD e 0 0 n e ig l b n a E T 2 no u n T i n e N t o d A. n t n u n u l P h i l m 1 l o a I C H P _}}