ML20040C073

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Viewgraphs from NRC 770118 Meeting W/Util & Westinghouse Re Insp of Steam Generators & Steam Generator Repairs
ML20040C073
Person / Time
Issue date: 01/18/1977
From:
NRC
To:
Shared Package
ML13319A635 List:
References
FOIA-81-313 NUDOCS 8201270233
Download: ML20040C073 (46)
v • d • e


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'P INTR 0 DUCTION

1) PURPOSE OF fiEETIllG IS TO REVIEW RESULTS OF SCE INSPECTION PROGRAM '.fr!ICH ALS0' INCLUDED DRILLI!:G 3-INCH ACCESS OPENING AND CONTRIBUTION OF RESULTS TO ACCO '.PLISHMENT OF.0BJECTIVES.

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IN ADDITION, FOLLOWING ITEMS WILL BE DISCUSSED:

.A.

SAFETY ASPECTS RELATIVE TO' LOWER SUPPORT PLATE FLOW SLOT DEFORMATION (HOURGLASSItlG).

B.

CONDITION OF STEAM GENERATOR TUBES AND ANTIVIBRATION BARS IN U-BEND AREA.

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VIDEO GRAPH A.

HANDH0LE ENTRY INSPECTI0h5 1.

INTRODUCTION--DESCR!CE STEAM GENERATORS STEAM GEi!ERATOR SKETCH-2.

VI5UAL I"SPECTIC:1:: ACE DURING EDDY CURRE:;T.

TESTING CECAUSE OF LARGE itUMBER OF IflDICATIO:iS 3.

HAicD HELD cat'. ERA--0ESCRIBE TECHNIQUE FOR STEAM GENERATORS "A",

"B", AND "C" 4.

PERISCOPE APPARATUS--DESCRIBE TECHNIQUE PERISCOPE APPARATUS 5.

RESULTS OF IftSPECTIO:tS FLOW SLOT DIAGRAf1 PHOTOGRAPH BOOK

-B.

UPPER BUNDLE EitTRY -

"A" STEAM GENERATOR

'l.

DISCUSS RESULTS OF VIDEOTAPE OF FLOW SLOTS VIDEOTAPE ArtALYSIS C.

EDDY CURRENT PROBING INSPECTI0!tS 100 KHZ EDDY CURRENT PROBE INSPECTION 100 KHZ RESULTS 1.

DISCUSSRESULTSOFROWS1TO5,COLUfkNS 1 TO 100, FOR ALL STEAM GENERATORS 400 KHZ REDUCED GAIN DENT SURVEY l

1.

INSPECTION PLAN A, B, AllD C STEAM 2.

RESULTS IN "A" A!!D "C" STEAM GENERATORS GENERATORS, TUBESHEET 3.

RESULTS IN "B" STEAM GENERATOR MAPS D.

DRILLIttG OF THREE INCH HOLE IN "C" STEAM GEllERATOR 1.

LOCATION OF HOLE

~ STEAM GENERATOR SKETCH 2.

DISCUSS PICTURES OF FLOWSLOTS PHOTOGRAPH BOOK 3.

FLOWSLOT GAUGlHG--FLOUSLOTS 1, 2, 3 FLOWSLOT DIAGRAM

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SAf) ONOFRE NUCLEAR GENERATING STATION - UNIT 1

SUMMARY

OF SUPPORT PLATE FLONSLOT CONDITIONS BASED.

0" A"ALYSIS OF VIDEO TAPE DATA Slot Numbec -

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3 4

5 6

STEAM GENERATOR'C No Deformation No Deformation 1

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.p 4th Support Plate NOTE:

1. Inspection of Steam Generator "A" was completed using the tooside bundle inspection technique usina a fiberscope/TV camera
2. Insoection of Steam Generator "C" was comnleted by using a fiberscone/lV camera

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technioue throuah a three inch hole in the steam generator shell.

3. Sketch not to scale.

January 18, 1977 R

~ SAtt Ot10FRE fiUCLEAR GEtiERATIriG STATI0ti - UtilT 1 100 KHZ SURVEY fl0 IflDICATI0 tis WERE F0UtID Ifl Tile U-BEtiD AREA 0F T110SE TUBES TESTED Ifl A, B, AtlD C STEAM GErlERATOR.

R0WS 1 TliROUGil 5, COLUtitlS 1 TO 100 WERE TESTED.

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January 18, 1917

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SArt Ot10FRE flVCLEAR GENERATING STATI0ft - UtilT 1 Steam Generator A Inlet 9991959391 ff187 8583 8119117511716967L5145I.I M 57 5555 5143 47 45434t h'8513555 3:1.917 z52316 39 l] s 513 ll qps3:

COLUMNS 4,%9L 14?l lo BSB684 82 Sc le 7t. 74 72 10 Lt LLlA616058 5L54 52564840 41 42 4o 38 3 r.34 52 30 287& 24 ti to is e t, 14 12 to 8 L, 4 2

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l 0 400 Kill (Reduced Gain;i Through 4th Supp3rt

  1. 400 Kill (Reduced Gain i Through U-Bend and Through Outlet Side January 18, 1977 f

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. Sari OriOFRE fiUCLEAR GEf1ERATItG STAT 10ri - UtlIT 1 STEAM GEtiERATOR A OUTLET

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r SAN ON0FRE NUCLEAR GENERATING STATION - UNIT 1

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s SAtt OfiOFRE tiUCLEAR GEt1ERATIrlG STATI0ft - UtilT 1 Steam Generator C

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-M A NWAY NOZZLE January 18, 19//

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Relationship or SCE-Inspection Results to Overall Questions of Tube Denting and Suecort Plate Flcu Slot Heuralassing A.

Brief review-of current status on other plants 1.

Centers on Top Support Plate i

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Effect"on U-Tubes i

B.

Effects have been analy:ed and quantified 1.

Preventative maintenance plugging

2.. Monitoring program of inspections j

C.

SCE Relationship l

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Inspections have shown that the condition does not exist a.

Support Plates b.

Dented Tubes

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Conclusion J

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No plugging program required for denting.

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No need demonstrated for inspection prior to next refueling.

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CRACK ING OF SUPPORT PLA TE LI GAMEN TS 1..

Tleasile stress i n liga: men:ts tres corros i on product expan:siiton..

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Turkey P c i nt on d Surry sampfbes:

- Approximately 75% of ligamennts

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Cracking not caused by common ductile failure.

4 Probable failure mechanisa:

- Oxide Wedging 5.

Tubes held i n place by compressive forces.

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i STEAMLINE BREAl' C O N S I D E R A T I C;. S 1.

Fragment Effects 2.

Flow i nduced Vibration a.

U-bend Region b.

Wrapper Opening 3.

High Pressure Drops Across Support Plate D

4 l

l e

G 6

0 e

l

7

.\\

SUPPORT PLATE FR AGMEN TS 1.

SLB. hydrodynamic analyses.

\\

\\

2 P ro: ject ile impact te.sts on tubes.

k 3.

Impact veloci ties up' to '100 f t/sec.

4.

Burst pressures of damaged tubes essentioily unchenged.

STEAMLINE BREAK DYNAMIC PRESSURE TIME HISTORY '

~

Dynamic pressure (Pal)

~

i i

-)

j 1.30 1.2.0 -

l 1.10 -

l 1.00 -

.90 -

-9

.80 -

70 -

.60 -

.50 -

.40 -

.30 -

Locallon: top support plate Condition: no load

.20 - >r

-W

.10 -

.05 -

j 0

.T e

O 1

2 3

4 4

6 7

t Time (sec.)

l io is4 2o m

-a

m...-

_ w m _ m,.

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y..

_;. :T.

......r.-

=.==e

-- =

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-; =y.m w;c.c =+;aa: 4. g= ;,;~,;.;.g gm3= m --3 <.

-.--m.

.-r :E- :.:. >=::-AR::5';-,3;;.;.

=

- - :.u

.n-

.=-

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...:..:........;-.:.....:,.,.,.; ;. w..y.

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7 m.:. r.v.=,. :.~ :: z., m :.---...

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' '...-

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4 TUEE FRETTING AND AER A510N TESTS 1.

Postulated accident conditions (SSE,

SLB, FLB, LOCA) were analyzed to ob-tain maximum values for:

~

- tube vibration amplitudes

~

~

(0.375 inches)

- contact forces (75 lbs.)

duration of. loading (10 seconds)

~

2.

Tubes for'ced to vibrate within broken suppo'rt plate annulus.

3.

Burst pressures of damaged tubes essentially un: changed.

I

TUBE VIBRATION TEST APPARATUS

.75" gmplitude of vibrallon for 10 seconds at Integral tube sup.

,g plate Vib.

Broken tube y support piple y arm 11 m

h M'

N' N'

_s

.s 16.81 -

=

36

-A 72 1

8@

Removed

_{_

j 4 y

support Y

Y g ent\\

',+

+

e++e

+

+

+

10. i s t.n

+

e

..........e.e

a. =

. :,.x.,.,..

z. -g._.;. p.

y p-- u.= =:-~ c: :w. - m:- -, ww :a :pc m_m:i y.. n c %. & ~: flag - q.=.._.. w...,-....,..

e s=--

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.e

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.w.

Q

' %2=

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F

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.?

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=

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=

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wwnn,

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=,

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A.

Figura 13-5.

Photograph of Tub'e Sample D-6 af ter F.xperiment I

i.f f, 1. @ ; g,'f;.'y M S 4.ad

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. :.O.:

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s

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Figure 13-6.

Photo 3;rzph of Tube Sa=ple D-7 af ter F.xperiment.

13-10

  • "t eo

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g n gra r--

R.

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n

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Aut as s ar j

FIG.1 - Dented tubes af ter burst testing.

l (Tube B-2 not burst tested but shown l

to indicate the dent that was in B-1).

I l '2.h

3UE3T FRE33URE IE3I RE321~2 Burst Pressure' Tube psi Gi* 6 ' '

A -1 11,000 clug 3'_ar i

A -2 9,800 Plug Slew Gut B

,1 8,500 Ruptured in Dent B -4 9,000 Plug Blew Out C -2 9,700 Plug Blew out D-4 11,000 Ruptured Outside Dent 0-7 10,800 Ruptured Outeide Dent TY P E O F LO A D l'N G Series A:

Impact Exp.eriments

! Series 8:

Shear Tests Series C:

Support Plate Crush Experiments Series D:

Tube Vibration Te s ts l

l FC

DISCUSSIO:10F STEA:1 GE::ERATOR TU3ES A::3 AriTIVICP.ATIC'! CARS I:t U-BE::D AREA VIDEO GRAPH A.

EDDY CURRE:!T I:lSPECTICil 0F U-BE!iD 1.

INSPECTIC!i PLA' TUBESHEET MAP 2.

RESULTS AVB RESULTS 3.

REASO:t FOR THII::11t!G -- FRETTING ATTACK 3 TUBES. 2 AVB'S MOVED F,0R ANALYSIS i

B.

A',TIVIBRATIO:t BAR MODIFICATIO:t 1.

LOCATIO:! 0F !!E'.! AVB'S AVB MODIFICATION 2.

NEW AVB C0:;STRUCT10il 3.

STATUS OF IliSTALLATION 1

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SAN ON0FRE NUCLEAR GENERATING STATI0ri - UrtIT 1 Steam Generator B O

919191*TA' l @ EU 8583 0119111513 7t f.9t.7L51,3&l *Ji s7 55555s ti 4145 4548 5%135 n 341.917 2513 2 s tf il :51311 4 7 5 3 I I

l COLUD/.NS imw.

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W MANWAY NOZZLE - D-A TUBE PLANNED FOR PLUGGlHG TUBE PREVIOUSLY PLUGGE F-

~

January l!!, 1977 l

e

=

SAN uaut:tt HULLtnri utntnne ano s one *wn va-*

Steam Generator C s

u l

- l 919195139t tr18? D583 88191175117LL967LS1,$Li 'A 57 55515643 4145 43 4t sis 155 351:1.917 zsts 28 89 81 5 318 4 7 5 3 i 8

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g ROWS MANWAY NO7.ZLE I>-

b TURE PLANNED FOR PLUGGillG f

0 TUBE PREVIOUSLY PLUGGED January 18, 1977

+

- RAN ONOFRE NUCLEAR GEilERATING STATI0ft - UtlIT 1 i

'ANTIVIBRATION BAR AREA INDICATIONS STEAM GENERATOR A

B C

NUMBER OF TUBES TESTED 1790 1879 1727 PERCENT INDICATION

^

<20%

5 7

6 21-29%

14 14 24 30-39%-

47 70 60 40-49%

17 32 28 0

50-59%

2 13 16 60-69%

1 0-19 70-79%

0 0

4 80-89%

0 0

2 TOTAL 86 136 159 Number of tubes with AVB defects > 50%

3 13 41 LOCATION OF DEFEC.TS A_

B C

AVB #1 30 35 95 AVB #2 25 47 95 AVB #3 22 36 106 AVB #4

  • 16 30 90 Number of tubes with 5

10 98 multiple defects January 18, 1977

,..; e...w.... :.... ;,,... u c.. ;..a.... a..._....-.n....

a

.v..

~

...:.a.:..........

- - - - -- ??.07 C ~ D '.' 2/J. ;JJ.L': Z'T.'C C

,,r O

Af ~ %

400 Ms 400

's i

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s

't s'

s s

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l s

s

's t

t

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j s'

N

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i.

_I I

TI*BE RO:7 48 23 17'14 14 17 23 48 PROPC;2D AR.RANGDCC

Add V 3ars Between E.tseing V 3ars and Attach to F.xisting Retainer Ring b

NOTE: The crocosed modification affects tubes in columns 18 throuah 83

~

inclusive.

. January 18, 1977 4

Laborator$/ Examination of Removed Antivibration Car and Tube Sc: roles 1.

Antivibration Bar A.

Dimansions at affected locations B.

Metallography at affected locations and undamaged regicns C.

Micro-hcrdness traverse 2.

Tube R46-C61 Hot and Cold leg A.

Radiography at affected locations

~

B.

Dimensions at affected locations C.

Matallography, Optical and Scanning Electron Microscopy EDAX Surf.~ce Analysis

' D.

a E.

Micro-hardness traverse 3.

Conclusions Damage was caused by a wear mechanism due to reTative motion of the components.

There is no evidence of a chemical attack at the intersecting locations.

9 4

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SK ETCH SHEET

  • ELTINGh0U S E EL E CT RIC CO R P Ok ATION 4

I l

THlMMIMCr OF SC E C.ARBOM STEEL AN O 's Nominal Diosna.bc.c

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COLO LEG i

LOJER 6AR UPPER. 6AR i

l

. - -. n c

25 -

51 SERtEs 20 STEAM qEME.RATOR.

+

~-15 6

Iwa

$10 WEA2. AT SUPPORT PLAT *_.

d4d 3

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no 20 30 40 SC PADtAL CLEARAMCE mt $S 3

WEAR. OEPTA yERsus CA.E ARA.M CE-FLuit ELAST1C

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FtGORE.

1-5 4

1-9

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C 51.mle (Bottom !! Bar)

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Span - 45.25" 3

4 v = 50 #/ft 0

<p D,G DG)d DC)G SL71e (Nodes 11, 57)

+

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e 3

v = 50 J/ft 3fgj f l l

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+

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F1:ced (Tubesheec) (Modes 1, 67)

Rows 48 36 24 2c 36 48 Figure 2-1.

SCE Steam Generator Tube Vibration Analytical.Models for Tube Rows 24, 36 and 38 (Support Case 1) 2-2 nO

~

Sinole (Top V 3ar)(Nodes 32, 36)

U-Bend Region

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'irapper Opening --*-

U = 11.1 fps

  • 6 3/.

4 + Fixed (Tubesheet) (Nodes 1, 67) i e,-ibe,,,,

Revs 48 36 24 24 36 43 l

l

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Figure 2-2.

SCE Steam Generator Tube Vibration Analytical Models for News 24, 36 and 38 (Support Case 2).

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CDC Ck3 2

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1, Figure 3-6

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9

2.5 -

A TU2E SUPPORT CASE 1

,0 U

O nisE sUPPoRr CASE 2 u.

m N

m

C I

f 1.3 _.

C 3

-c<s tr.

Cp UNSTABLE REGION g

1.0- - - - - - - - - - - - - - - - - -

STABLE REGION 1

0

-e us 3

u c

50.5.

~u.

l t

l

)

I j

0.0 l

10 20 30 40 50 i

TUBE BEND RADIUS, INCHES l

l l

l 1

10 24 36 48 l

TUBE RO'1 NUMBER l

Figure 4-1.

SCE Steam Generator Tube Vibration Analysis Results.

l t

4-5 i

l r l'9 t

T

--'?

Tn--

i f,fi,f[.

  • E W ESTINGHOUS E EL ECTRIC CO R POR A TION I

5CE Tose Ptuec=lMCr C R \\T E RlA.

SUMMARY

top Ave ANS ALL DEFEC.T LOCAT1Ohl R ATE g)

(Q omEst Min. Gall ThicKnc.ss Tkcmitred 50% 50%

loo % 50%

Kin. LJail ThicKna.ss Requica.d 47% 40%

40%

40%

Max.. Dqradak Allowed 3*/.

Lo%

Yo0%

to%

NOTES:

O)

Columns (8-83 GO Columns t.2.-t7, 84-89 ; Roo)s 30 -%

U2

.Y."A"/" 5 "

W ESTINGHOUS E ELECTRIC CORPOR ATION TEcHMtLAL BASES FO R MI Mt MOK L) ALL TMcK. NESS REQOtRED A..

blormal Ocarakng CondAgns

%sS g

?6urst 3 3Pcpu.Wn$

~

~

B.

Faut.kd CandMens t.

LOCA + SS E

% + % 6.1{ t. o s S w

~

? s o.9 bg 2.

FL6 or SL6

% 5 0.7 Sw C.

se.condorw side Leax Test

~

6

0. 8 Pcotag,c I

i

~

, ev eveu qEET

,;..:nt-W ESTlHCHOUSE EL ECTRIC CO RPOR ATION SCE STEAM GENERATOR TUBE EC INSPECTION DATA 100 -

AVERACE RIBE V-BAR DEFECT 90 -

AT EACH IN9DECTION DATE 80 -

70 -

c 60 -

O 5

s.a 50 -

pA H

/

g

/

l 40 -

/'

30 -

,/

G, 20 -

SG C [ -

10 -

/

/

0 i

7 67 68 69 70 71 72 73 74 75.

76 77,,.,

YEAR PRE 1973 DEFECT RATES ( / YEAR)

SG A SG B SG C 20 27%

28

= 3.4

= 4.2

= 4.3 5.8 6.5 6.5 tf o

e*

PCSS:"*.: 02-^E:T "-

1)

SINCE INSPECTI.hN OF UPPED SUPPORT PLATES 5;:3'..' :;0 DE iTING OR FLOW SLOT DEFORMATI0ri IN STEA:1 GE;!ERATORS, flEITHER PREVENTATIVE TUBE PLIJGGIriG tiOR A:: IllTERIi1 SHUTP,0'.::: FOR lE!!!SPECT!0:i TO ASSURE IrlTEGRITY OF SMALL RADIUS STEAM GE:ERATJR TU2ES ARE WARRANTED.

I:ISPECTIO:1 PROGRAM DURII;G NEXT REFUELI:!G OUTAGE WILL CONSIST OF:

A.

PHOTOGRAPHING FLOW SLOTS I:1 UPPER SUFFORT PLAT'ES IN STEAM

'~

GEllERATORS A A:;D G THROUS:1 HA:: DHOLE E::TRY.

B.

E00Y CURREriT PR03ING 1:! SPEC'TIO:10F ALL TUBES II: R0WS 1 THROUGH S AROU:1D U-GE?lD IN STEAM GEf;ERATORS A, S, A;;D C.

C.

PHOTOGRAPHIl!G AND MEASURING FLOW SLOTS !!! UPPER SUPPORT PLATE l

THROUGH 3 INCH ACCESS OPE!:I!G IN STEAM GENERATOR C.

l

2) SINCE THERE 'ARE i;0 SAFETY C0i!SEQUE!!CES WITH C0i!TI!!UED OPERATION UITH

{0NDITION OF LOWER SUPPORT PLATES, A PROGRAM OF CORRECTIVE ACTIO:IS IS NOT WARRA!!TED.

3) A.PROGRA'i 0F CORRECTIVE ACTIOilS TO ASSURE C0;4TINUED SAFE OPERATIO 1 WITH CC:DITION OF STEAM GENERATOR TUEES A!D ANTIVIBRATI0tl BARS IN

.U-BEND AREA HAS BEEH IIIPLE!!ENTED.

4 A.

NEW ANTIVIBRATION BAR I!!STALLATION.

B.

PREVENTATIVE TUBE PLUGGING FOR ALL AFFECTED TUBES SUPPORTED BY.

1 NEW ANTIVIBRATIO;f BARS WITH IrlDICATIONS EQUAL TO OR GREATER THAN SO%.

C.

PREVEllTATIVE TUBE PLUGGIt!G FOR ALL AFFECTED TUBES NOT SUPPORTED BY NEW ANTIVIBRATION BARS (ROWS 30-36 COLUMNS 12-17 and 84-89) i WITH MEASURED IriDICATI0rlS'(EVEN < 20%).

SEE TUBE PLUGGING CRITERIA.

INSPECTIO!1 PROGRAM DURING NEXT REFUELING OUTAGE WILL C0!!SIST OF EDDY CURRENT PROBIT:G INSPECTION OF A.L TUBES IN AREA 0F A.1TIVIBRATION BARS, IN ROUS 20 THROUGH 48, COLUEIS 18 THROUGH 83 AND ALL TUBES IN R0WS 30 THROUGH 36, COLU:lilS 12 THROUGH 17-Afl0 COLUMNS 84 THROUGH 89.

I g i

l 4

a.

TU3E PLUGGING CRITER!A S. G.

S. G.

S. G.

A 3

C TOTAL

> 507. AVE CEFECT 3

13 41 57

> 507. TU3ESEEET DEFECT 12 0

0 12

~

IN TRIANGLE 12 5

8 25 LEAKING 3

0 0

3 R

0VED FdR AliALYSIS W

3*

3*

TOTAL 30 18 51*

99*

PREVIOUSLY ELUGGED

~ ' 21 11 49 81 GRAND TOTAL S1 29 100 180 i

l l

c I

TOTAL TU3ES IN EACH STEAM GENERATOR - 3794

(*) "THREE TUBES REMOVED FOR ANALYSIS - OME CONTAINED AN AV3 DEFECT

> 507..

l

_. -.

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