Text

Slide Presentation Entitled, Ginna Station Steam Generator Evaluation NRC Meeting,820430
	ML17256A932
Person / Time
Site:	Ginna
Issue date:	05/07/1982
From:	; Office of Nuclear Reactor Regulation
To:	;
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GINNA STATION STEAM GENERATOR E9'ALUATION NRC MEETING APRIL 30, 1982 KIIJMm7 MRH FILLNB, 8205 1 4024 '000P44 pDR ADQCK 0500

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GINNA STATION, STEAM GENERATOR EVALUATION NRC MEETING APRIL 30, 1982 AGENDA o

INTRODUCTION R.

C. Mecredy o

INSPECTION RESULTS A. E. Curtis o

FAILURE ANALYSIS PROGRAM L. F. Ermold o

B-STEAM GENERATOR REPAIRS J.

C. Noon o

TECHNICAL BASIS FOR REPAIRS L. F. Ermold o

SUMMARY

J.

C. Hutton

GINNA STATION STEAM GENERATOR EVALUATION NRC MEETING APRIL 30, 1982 OBJECTIVES o

DETERMINE THE FULL EXTENT OF DEFECTS o

DETERMINE THE TUBE FAILURE MECHANISM(S) o RESTORE THE STEAM GENERATOR TO A CONDITION WHICH IS SAFE TO OPERATE WHILE MAINTAININGRADIATION EXPOSURES AS LOW AS REASONABLY ACHIEVABLE o

OBTAIN NRC CONCURRENCE FOR RETURN TO POWER

GINNA STATION STEAM GENERATOR EVALUATION NRC MEETING APRIL 30, 1982

'PURPOSE OF. MEETING o

TO REVIEW STEAM GENERATOR EVALUATION REPORT DATED APRIL 26, 1982 o

.SUMMARIZE RESULTS OF TUBE FAILURE ANALYSIS PROGRAM o

PRESENT CONCLUSIONS AS TO REASONS FOR JANUARY 25, 1982 TUBE RUPTURE o

IDENTIFY ANY ADDITIONAL INFORMATION REQUIRED FOR

.TIMELY COMPLETION OF SER

GINNA STATION STEAM GENERATOR EVALUATION NRC MEETING APRIL 30, 1982 NSARB C REVIEWS o

CONCURRENCE WITH PROGRAM CONCEPTS NSARB - 2/26 NRC

- 3/1 o

APPROVAL OF REMOVAL OF METALLURGICAL SAMPLES NSARB - 2/26 NRC

- 3/1 o

APPROVAL OF REPAIR PROGRAM NSARB - 3/16 NRC - 3/23 o

APPROVAL OF RETURN TO POWER NSARB - 5/10 NRC

- 5/14

I I

H

GINNA STATION..

STEAM GENERATOR EVALUATION NRC MEETING APRIL 30, 1982 STEAM GENERATOR CONFIGURATION AND OPERATING HISTORY o

CONFIGURATION o 'PERATING HISTORY o

CHEMISTRY o

'LUGGING o

SECONDARY SIDE MODIFICATIONS

JANUARY 1976 PERIPHERY AREA DEFECTS GI

.STATION STEAM GENERATOR EVALUATION NRC MEETING APRIL 30, 1982 B-HOT LEG (INLET)

RGLE Steam Generator eII 8561I~St 1911157'5 7 I L967 L5L3 LI59 57'$5 53 5 I%9 4:7 45 45 41 3937 3533 3l 2927 25 23 2l l9 I7 l5 l3 I I 9 7 5 3 I

~

'OLuM~S

$ 2 ')0 EB 82 7Z 70 8 64 62605 56 54 52 5 4

46 44

'5323 28 2.lo 22 I8 I6 I412 IO WEDGE AREA NUMBER 4 R40 C68 LEAKER:

~

WEDGE AREA NUMBER 8

~

45 44.

42 43 4l 40 39 32 33 3I 30

.28 26 23 22 2I 20 I8 I6 I4 15 I2 II IO 8

6 2 '

I

~

ROWS NOZZLE~

Sheet.

1 of 10 37 WEDGE AREA NUMBER 2 5<

I GI A STATION

'STEAN GENERATOR EVALUATION NRC NEETING MAY 1976 PERIPHERY AREK DEFECTS 8-HOT LEG (INLET).

APRIL 30, 1982 RGLE Steam Generator I.

9I S18165EPSt1'I1118'I57I I9LIL5LEL16'157'6553514'I41454541 3937 353531 29272523211917 15 1311 9 7 5 3 I

COLUMNS 127O a<I. I4 <2I,O 525 4

4I 44 42

'bio '1323 282.L 22 18 16 14 12 10 64 2

WEDGE AREA NUMBER 4

~

4

~

R12 C91 LEAKER WEDGE AREA NUMBER 6 24 22 20 16 14 12 10 ROv/S 2

44 42 4O 38 WEDGE AREA 36 NUMBER 2 ~4 32 30 28 45 43 41 39 37 35 33 31 29 27 25 23 21 l9 17 15 13 II 9

7.

5 3

I

~MANWAY NOZZLE~

Sheet 2 of 10

c I

f"

GI

.STATION

'STEAN GENERATOR EVALUATION NRC NEETING APRIL'30, 1982 JULY 1977 PERIPHERY AREA DEFECTS B-HOT LEG (INLET).

RGsE Steam Generator 91 858785 &81 '1911757'5 71 L'961 65l '361 59 57'QS 535149474545 41 3937 3533(31 29272523211917 15 13 I I 9 7 5

3 COLUMNS 8Z 8 I 74 72 70 8 LL 64 62 60 525 44 42, o 3

3Z 3 ZSZ.L 22 18 16 14 12 IO 64 2

WEDGE AREA NUMBER 4 R4 5 C54 LEAKER

~

44.

4O 45 43 41

~

WEDGE-AREA NUMBER 6 38 37 WEDGE AREA 36 NUMBER 2 ~4 32 31 30

.28 26 23 21 20 18 16 14 15 13 II IO 8

6 4

2-.

I ROWS

~ IVIANWAY NOZZLE~

Sheet 3 of 10

~

NA STATION STEAM GENERATOR EVALUATION NRC MEETING

~ APRIL 30, 1982 JANUARY 19 PERIPHERY AREA DEFECTS B-HOT LEG (INLET)

RGSE Steam Generator 91808755&81191115T571 L8676SLEll59$15553514941454341 393735$ 33129272523211917 15 1311 9 7 5

3 I

82 72 64 62 605 56 54 525 4

46 4424 I

I I

I 3 36

%32 I

I I

I 3

ZB 22 18 16 14 12 IO COLUMNS 2

WEDGE AREA NUMBER 4 R4 4 C54 LEAKER WEDGE AREA NUMBER 6

~ MANWAY 44 42 4O 38 WEDGE AREA 36 NUMBER 2 30 28 26 22 20 18 16 12 IO 8

ROWS NOZZLE~

Sheet:

$ of 10 45 43 41 39 37 35 33.

31 29 27 25 23 21-19 17

'15 13 11 9

.7 5

3 I

GI A STATION STEAM GENERATOR EVALUATION NRC MEETING APRIL 30, 1982 l

APRIL 1978 PERIPHERY AREA DEFECTS B-HOT LEG (INLET)

RGaE Steam Generator 9l 858755838I19111575716967LSLELIER'6755535I494145454I 3937353331 292725232I l9I7 l5 l3 II 9 7 5

3 I

~

'I COLUMNS Q2 ')0 82 72 70 8 64 62 605 SL54525 442 36 'f323 28 22 IB I6 I4 I2 IO WEDGE AREA NUMBER 4 WEDGE AREA NUMBER 6

~ MANWAY 45 44 42 43 4I 4O 3S 37 WEDGE AREA 36 NUMBER 2 ~4 32 33 3I 30 28 26 23 22 2I 20 I6 I4 l2 I I IO 8

2 ~

I ROItS NOZZLE~

Sgpet 5 of 10

GI A STATION STEAM GENERATOR EVALUATION NRC MEETING FEBRUARY 1979 PERIPHERY AREA DEFECTS B-HOT LEG (INLET)'

B APRIL 30, 1982 RG6E Steam Generator

~ 91 O'I1765fSSI l911157571 L96765L36I5'I57'$555514947454541 39373533/1 29272523211917 15 1311 9 7 5

3 I

COLUMNS-89 86 52 74 270 8 64 6260 54 52 46 44 424 3

36 'f323 262.6 22 1816 14 12 10 64 2

WEDGE AREA NUMBER 4

~

WEDGE AREA NUMBER 6

~ MANWAY

~

42 4Q WEDGE AREA NUMBER 2

- ~4 32 30 28 26 22 20 18 16 14 12 IO ROWS NOZZLE~

Sheet 6 of 10 45.'3 41 39 37 35 33 31 29 27 25 23 21 19 17 15 13 II 9

7.

5 3

I

GI A.STATION STEAN GENERATOR EVALUATION NRC MEETING APRIL 30, 1982 DECEMBER 1979 PERIPHERY AREA DEFECTS'-HOT LEG (INLET)

RGSE Steam Generator I

9l 8')8755&8I191~1151571L9676SL3615957 55 535IO9414545 4I 39373533/I 2927252321 I9 I7 l5 l3 I'I 9 7 5 3 I

COLUMNS

. )z ')oB8 12 0 86664 62605 525 44424 36 'f32 282.6 22 I8 l6 14 l2I08 6 WEDGE AREA NUMBER 4 R4 3 C54 LEAKER 44 4Q 45 43 4I WEDGE AREA NUMBER 6

~ MANWAY 38 37 WEDGE AREA 36 NUMBER 2 ~4 33 3l 30 28 26 25 22 23-2I 20 I7 16 14 II IO 8

7 5

2.-

3 I

ROWS NOZZLE~

Sheet 7 of 10

GINNA STATION STEAN GENERATOR EVALUATION NRC 11EETING-APRIL 1980 PERIPHERY AREA DEFECTS ~-

B-HOT LEG (INLET)'

APRIL 30, 1982 RGaE Steam Generator l,

(4 eII SNSTSSRSI191175't3 7I I96765L3615'I5755 535IO9414545 4I 3937353$ 3I 292725232l l9 I7 l5 l3 II 9 7 5

3 I

COLuM~S 92 ')O88SI 12 70 Sgl 64 6Z 60 54 5Z 4l 4 424 3

3l'o '}32 28 6

22 IB I6 l4 l2 IO 4

2 WEDGE AREA NUMBER 4

~

WEDGE AREA NUMBER,6.

~

44, 42 4O 38 WEDGE AREA 36 NUMBER 2 30 28 22 20 IB l2 IO 45 43 41 39 37 35 33 3I 29 27 25 23 2I l9 l7 I5 l3 II 9

7 5

~ MANYYAY

.,BOAS NOZZLE~

Sheet 8 of 10

GINNA STATION STEAM GENERATOR EVALUATION NRC MEETING'PRIL:1981 PERIPHERY AREA,DEFECTS B-HOT LEG (INLET)'PRIL 30, 1982 RG6E Steam Generator

~

)

eII O'I6755&8I1911757'57I l96765I %61595755535)49474543 4l 393735333l 292725232l l917 l5 13 II 9 7 5 3

')0 88 86 52 70 86664 62 60 54 52 4424 3

3 282.l 22 I816 l4 I2 IO 8 6 COLUMNS 2

WEDGE AREA NUMBER 4

~

45 42 4l 4O 38 WEDGE AREA 36 37 NUMBER 2 ~4 WEDGE AREA NUMBER 6

~

BOAS 32 31 29.

26 25 22 23 2l 20 I

I6 17 I5 I4 II IO 8

6 4

2.

I

~ MANWAY NOZZLE~

Sheet.

9 of 10

t GINNA STATION STEAM.GENERATOR EVALUATION NRC MEETING'ANUARY 25, 1982

'ERIPHERY AREA DEFECTS B-HOT LEG (INLET)

APRIL 30, 1982 RGSE Steam Generator 4

91 85876582811911'757571I9L7LSt EL1595755535149474543413937353/3129272523211917 15 1311 9 7 5

3 I

COLUMNS.

74 72 70 8 64 6260 S SL 54 525 46 44 42 323 28 2Z 18 16 1412 IO VtEDGE AREA NUMBER 4 R42 C55 BURST WEDGE AREA NUMBER. 6-

-ca-MANVIAY 45 44 43 41 4O 39 38 WEDGE AREA 36 NUMBER 2 ~4 32 33 31 30 28 26 25 21 20 IS I6 15 13 11 IO8-6 5

4 2-I ROYYS NOZZLE~

Sheet 10 of 10

GINNA STATION, STEAM GENERATOR EVALUATION NRC MEETING APRIL 30, 1982 STEAM GENERATOR INSPECTION RESULTS o

EDDY CURRENT EXAMINATION o

PROFILOMETRY EKAMINATION o

FIBER OPTICS INSPECTION o

TELEVISION VIDEO INSPECTION o

FOREIGN OBJECTS

C I

I

.0 GINNA STATION STEAM GENERATOR EUALUATION NRC MEETING APRIL 30, 1982 CATEGORIZATION OF DEFECTS CATEGORY 1.

Structurally Degraded 2.

Video OD Indication NO.

6 WEDGE AREA R8C92 R10C91 R11C91 R12C91 R14C90 R15C90 R9C91 R13C90 R16C89 R17C89 R40C70 AREA R38C71 R38C72 R39C68 R39C69 R39C70 R42C55M R43C53 R43C54M R43CSSM R43C56M R43C57 R43C58 NO. 4 WEDGE AREA R43C59 R43C60 R43C61 R44C52 R44C53M R44CS4 R45C51 R44C55M.

R44C56 R44C57 R44C58 R45C53 R45C54 NO.

2 WEDGE AREA 3.

Eddy Current Signal

4. 'Preventatzvely Plugged R15C89 R35C75*

R40C67 R40C68 R41C66 R45C46

'45C47M,'"

R45C48 R45C49 R45C50 R41C55

'R42C54.

R42C56 R12C2 R28C12*

R30C15 R31C15 R32C15 R32C16 R33C15 TOTALS 28 7.

M Metallurgical Samples R45C52 pulled April 1978

plugged for cold leg, support plate intersection, O.D. indications

GINNA STATION STEAM GENERATOR EVALUATION NRC MEETING APRIL 30, 1982 METALLURGICAL EXAMINATIONAND FAILURE ANALYSIS o,

SITE PHOTOGRAPHY o

WESTINGHOUSE/BATTELLE COLUMBUS LABORATORIES o

MODEL FOR WEAR ORIENTATION COMPARISONS o

PHOTOGRAPHY AT 90 INCREMENTS o

RADIOGRAPHY AT 45 INCREMENTS o

.DIMENSIONING o

OPTICAL METALLOGRAPHY OF TRANSVERSE SECTIONS o

SCANNING ELECTRON MICROSCOPE FRACTOGRAPHY 0

~

0 KNOOP MICROHARDNESS DETERMINATION ELECTRODE DISCHARGE SPECTROSCOPY CHEMICAL COMPOSITION 0

PHYSICAL PROPERTY DETERMINATIONS

GINNA STATION STEAM GENERATOR EVALUATION NRC MEETING APRIL 30, 1982 METALLURGICALEXAMINATION AND FAILURE ANALYSIS CONCLUSIONS o

MICROSTRUCTURES WERE NORMAL o

MECHANICAL PROPERTIES WERE NORMAL o

NO EVIDENCE OF CORROSION OF ANY TUBE o 'NITIALMETALLURGICAL SAMPLES DISPLAYED WEAR ZONES OF O.D.

WALL REDUCTION WITH CIRCUMFERENTIAL STRIATIONS 38 OF THE 40 WEAR ZONES SHOWED KNOOP MICROHARDNESS VALUES INDICATIVE OF COLD WORK FROM THE WEAR PROCESS o

THE "BURST" R42 C55 OCCURRED WHERE THE WEAR ZONE HAD REDUCED THE WALL THICKNESS TO

< 0.008 INCHES FOR APPROXIMATELY 4 INCHES IN LENGTH o

THE "BURST" R42 C55 FRACTURE FACE WAS PURE SHEAR (DIMPLED RUPTURE),

THE NORMAL FRACTURE MODE FOR TENSILE OVERLOAD COLLAPSED AREAS OF PERIPHERY TUBES SHOWED EXTENSIVE COLD WORK 8-10 MILS IN DEPTH o

AREAS OF SEVER AND AXIAL BREAKAGE SHOWED FATIGUE STRIATIONS o

THE DEFECT 24" ABOVE TUBE SHEET ON R45 C47 WAS CAUSED BY RUBBING FROM SEVERED TUBE R45 C54, WHICH WAS WEDGED BETWEEN WRAPPER AND OUTER ROW OF TUBES

GINNA STATION STEAM GENERATOR EVALUATION NRC MEETING APRIL 30, 1982 POSTULATED FAILURE MECHANISM 0

INITIAL PLUGGING 0

COLLAPSE' SEYERANCE

~f 0

WEAR I'

~

CL tA

~ H

GINNA STATION STEAN GENERATOR EVALUATION NRC NEETIHG APRIL'30;"T982 Nechanical Load Active Tube Tube Plugged Collapse Vibration Shredding Sever Rear Plugged Tube Mear Active Tube Plugging Burst.

Postulated Failure Mechanism Sequence

G A STATION STEAM GENERATOR EVALUATION NRC MEETING APRIL 30, 1982 NO. 4 GE AREA JUL'Y 1977 ACCESS HOLE SHELL WEDGE R45 C54 LEAKER WRAPPER AWED

~e Qw +el 0 0 0

0 0 0 4

t 0

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0

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t 0 0

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42 4l 4Q COLUMN 6P.

6l 60 59 58 57 56 55 54 53 52 5I 50 49 48 47 46 45 Sheet 1 of 8

G' STATION STEAM GENERATOR EVALUATION NRC MEETING APRIL 30, 1982.

NO.

4 GE AREA

'ANUARY 1978 WCCF.SS Hot C

'I SHELL WEDGE R44 C54 LEAKER WRAPPER 4.

t 0 0 4

4 t

4.

0 0

44 0 0 42 4I 0

o o o 0

40 COLUMN 62 6I 60 59 58 57 56 55 54 55 52 5l 50 49 '8 47 46 45 Sheet 2 of 8

G A STATION STEAM GENERATOR EVALUATION NRC MEETING APRIL 30, 1982 NO. 4 GE AREA APRIL'978 ACCESS HOLE

'I SHELL WEDGE

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56 55 54 53 52 5l 50 49 48 4Y 46 45 Sheet 3 of 8

GI NA STATION STEM1 GENERATOR EVALUATION NRC NEETING APRIL 30, 1982.

NO. 4 GE AREA FEBRUARY '1979 ACCESS HOLE

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G NA STATION STEAM GENERATOR EVALUATION NRC MEETING APRIL 30, 1982 NO; 4 GE AREA DECEMBER 1979 ACCESS HOLE SHELL WEDGE R4 3 C54 LEAKER WRAPPER 0

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G A STATION STEAM GENERATOR EVALUATION NRC MEETING

'PRIL 30, 1982.

NO. 4 GE AREA

'APRIL 1980 ACCESS HOLE

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'56 55 54 53 52 51 50 49 '8 47 46 45 Sheet 6 of 8

G A STATION STEAM GENERATOR EVALUATION NRC MEETING APRIL 30, 1982

,NO. 4 GE AREA APRIL'981 ACCESS HOLE SHELL WEDGE WRAPPER

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G A STATION STEAM GENERATOR EVALUATION NRC MEETING

'PRIL 30, 1982.

NO.

4 GE AREA JANUARY. 25, 1982 ACCESS HOLE

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'62 6I 60 59 58 57 56 55 54 53 52 5l 50 49 -48 47 46 45 Sheet 8 of 8

GINNA STATION STEAM GENERATOR EVALUATION NRC MEETING

, APRIL 30, 1982 ANALYSIS AND TESTING PROGRAMS DESIGN PARAMETERS THERMAL HYDRAULIC EVALUATION FLOW INDUCED VIBRATION LATERAL IMPACT LOADS AXIAL LOADS COLLAPSE FATIGUE

'EAR/BURST COLLAPSE TESTING ',

FATIGUE TESTING MODEL TESTING CONCLUSIONS

GINNA STAT.ION STEAM GENERATOR EVALUATION NRC MEETING APRIL 30, 1982 DESIGN PARAMETERS NO LOAD STEADY-STATE Thot

=

T o1d

=, T

=.

547 F

P

=

2250 PSIA P

P

=

1020 PSIA 100%

FULL-POWER hot 603.8 F

Tco1d 547.7 F

T

'=

572. 5 F

Tstm

516.3 F

P

=

2250 PSIA P

P

=

777 PS IA

'TFW

=

414.7 F

REC IRC RATIO

=

4. 73

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GINNA STATION STEAM GENERATOR EVALUATION NRC MEETING APRIL 30, 1982 THERMAL HYDRAULIC EVALUATION

~ - PURPOSE DETERMINE FLUID VELOCITIES FOR.USE IN EVALUATING FLUID-INDUCED LOADS METHODS CHARM ANALYSIS WECAN ANALYSIS First Suppor Plate t ~

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, ~hrouqh Mrapper Opening

'D MEGAN Hydraulic Analysis

GINNA STATION STEAN GENERAT~ EVALUATION

,HRC HEEWNG APRIL'0, 19P2

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EOF SIDE COLD SIDE ClEKA MIIH TlSES FLUBBED BIN((A BASE CASE

STEAM GENERATOR EVALUATION

'RC MEETING APRIL 30, 1982

'7 f

(

. 4t Tsr x I7y COLD BIDE CIRLITT DISTRISlTIOU OF CD'ASE CASU 4

I.

6 4

Z 1st TSI TUBE'FtEET IOT SIX COLO SIX OUALITT OISTRIBUTIII OF 6IINA MITH.TUBES FLU66ED

(

GINNA STATION STEAM GENERATOR EVALUATION NRC MEETING APRIL 30.

] 982 NOMINAL AND BETWEEN-TUBE CROSSFLOW VELOCITIES IN AND NEAR THE PLUGGED TUBE REGION

.h,ocation Perimeter Cell (Face A)

Perimeter Cell (Face C)

Perimeter Cell (Face B)

One Cell in from P erimeter (Face B)

Crossflow Velocity

--- ~ (nominal)-

~ ~

~

8.2 ft/sec 8.2 ft/sec 9.01 ft/sec 8.54 ft/sec Crossflow Velocity one cell. of tubes lu ed 8.91 ft/sec 8.91 ft/sec

~

9.11 ft/sec 8.84 ft/sec Two Cells in from 8.21 ft/sec P erimeter (Face B) 8.56 ft/sec Node ll A

UA

GINNA STATION STEAM GENERATOR EVALUATION NRC MEETING APRIL 30, 1 982 FLOW'-

INDUCED VIBRATION PURPOSE DETERMINE THE STABILITY CHARACTERISTICS AND MAGNITUDES OF

'LOW-INDUCED VIBRATION DISPLACEMENTS AND/OR LOADS FOR HOT LEG TUBES BETWEEN THE TUBESHEET AND FIRST SUPPORT PLATEe METHOD 8

GROSS FLUID EFFECTS DYNAMIC BEHAVIOR OF TUBES WITH VARIOUS CROSS-SECTIONS SUBJECTED TO CROSSFLOWI I

LOCAL FLUID EFFECTS ESTIMATE MAGNITUDES OF DYNAMIC LOADS ACTING ON A TEAR IN STEAM GENERATOR TUBING

1 t

STEAM GENERATOR EVALUATION NRC MEETING APRIL 30$

1982

~ 675 IK 0.0..05 IK K(W. KALL UKEAR DIKKSICKS ~ IK YELOCIT Y ~

FPSX6 0'I 52.'2 SEC7IEARY FLUID CROSS FLOK REGINI

~

'p

'4.0'.0'.0 mASIC AKALYSIS INDEL.

GEOMETRY'UBE FUNDAMENTAL FREQUENCIES FOR THE VARIOUS CASES ANALYZED Cross Section Cylinder Flat 10 Oval ized Kidney Fixed-Fixed 0

58.7 HZ 48.9 HZ 58.3 HZ 58.2 HZ Pa0 40.3 HZ 31.6 HZ 40.0 HZ 39.9 HZ Fi xed-P inned P~ -1000 lbs 38.5 HZ 27-9 HZ

I STEAN GYRATOR EVAL'UATION NRC~REET I NG APRIL: 3P, 1982

~ l$ ~

fj FIXED-FIXED 80lYIDARY CNDITIONS DAKING RATIO ~ 0.01 FIXED-I'INNED BOUNDARY CNDITINS DAHPING RATIO ~'0.01 0

~ D0 caosi sknw Cl RCULAI}(

FLAT 10X OVALILED KINET 1ST lODE FRE. - HI "58.7, i8.9

'"58.3 SB;2

'TlSOL 0

00

~ b CIRCULAR FLAT 10X OVALIZED KINET 40.3 31.6 40.0 39.9 2.4 2.0 8

I EO 1.6' 0

,vl 1 2

.8 1.2

..-8

'UNSTABLE STABLE

~ < tS ~ '>,i 4.0 8.0 12.0 16.0:

00.0 CROSS FLW VELOCITIES ft/sec-,

~

'FLUIDELASTIC STABILITY RATIO OF TUBES AS A FNCTION OF CROSS FLDN VELOCITYo FIXED-FIXED

'AOWQARY.CNDITINS i.o, 8,0

~

1.0 16.0 20.0 CROSS FLDN VELOCITY - ft/sec WUIOELASTIC STABILITY RATIO OF TIRES AS A

FUNCTION OF CROSS FLQI VELOCITYo FIXED-PINNEO DO%DARY CNDITIONS

~

I

$ ) ~

~

ANNA STATION STEA~ENERATOR EVALUATION NRC MEETING APRIL 30, 1982

>I'

(

12.D CYLINDRICAL CROSS. SECTION TUBE SYHBOL AXIALPDRCE FIXITY g ao FF ao Fp 41000 lbs.

Comp F-P 24.

FLAT CROSS SECTION TURF.

SYHBOL AXIAL FORCE FIXITY 0

00 FF 0

o.o 4 1000 Ibs.

Comp.

F-P 10.

20*

8.0 I

lal CI I

6.0 16.

CI I

12.

4.0 8.

2.0 4.0 Alt

~I o 0

4.0 12.0 16.0 20.0 4.0 8 ~ 0 12.0 16.0 20.D CROSS FLOH YELOCITY FT/SEC PEAK RHS AHPLITUDE DUE To TURBULENCE AS A FUNCTION OF CROSS FLOH VELOCITY CROSS FLOH VELOCITY ft/sec PEAK RHS AHPLITUDE DUE To TURBULENCE AS A FUNCTIDN OF CROSS FLOM VELOCITY

GINNA STATION STEAM GENERATOR EVALUATION NRC MEETING APRIL 30, 1982

~ FLUID QLOCITT U

Tear IIodel for Calculating Vortex-Shedding Lo~x f ~ 5 U/D e i 2xf LIFT e CL (yfU2/2) III exp (4t)

DRAG ~ CO (ofU2/2) lo exp (4t)

TONNE ~ OL (sfU2/2) (NR/8) exp (Iwt)

VORTEX-SHEDDING INDUCED LOADS ON PROTRUSIONS FOR A FLUI.D.

VELOCITY OF 10.0 FT/SEC,:

1;0 1.0 1.0 1;0 1.0 5.0

~

5.0 0.1 0.20-0.30 0.40 0.50 0.50 1.00 5.0 1.50.

5.0 e.o 2.00 2.50 Ht'9 H. Inches Lift ebs

-28 (10-2)

.11 (10-1)

.25 (10-1)

.45 (10-1)

.70 (10-1)

.14..(10-1 )

.56 (10-0.13 0;22 0.35 Torque in-ebs

.35 (1&)

.28 (10-3);

.95 (10-3)

.22 (10 2)

.44 {10-2)

.18 (10 3)

.14 (10-2)

.47 {10-2,)

.11 (10-1)

.22 (10-1)

Lift a Torque Frequency.

HZ

.240 120 80

(.

60 48 240 120 80 60 48 Drag ebs

.28 (10-3)

.11 (10-2)

.25 (10-2)

.45 (10-2)

.70 (10-2)

.14 (10-2)

.56 (10x2)

.13 (10-1)

.22 (10-1)

-35 (10 1)

Drag Frequenc Hz 480 240 160 120 96

'480 240 160 120 96

STEAN GENERATOR EVALUATON NRC,MEETING APRIL 30, 1982 LATERAL.LOg3S PURPOSE ESTIMATE MAGNITUDES OF LATERAL'MPACT LOADS ON STEAM GENERATOR TUBESI NETHOD NON-LINEAR TIME HISTORY ANALYSIS OF FOREIGN OBJECT AND TUBE DYNAMICS'rapper Shell Uf Tube UF p

~ g-~x P

SG SG Qx F

(a)

TUBE BUNDLE ENTRANCE REGION WITH FOREIGN OBJECT (b)

SIHULATION OYNANIC NOEL OF FOREIGN OBJECT IHPACT

STEAN GENER~R EVAlUATION HRC 'HEING APRIL 30,".19'82 fOREIGN OBJECT'INDUCED LOADS

-. X (0)

Case

~inches Uss (ft/ esc}

Ug (ft/sec}

Model 1*

Peak Load

~lbs Hodel 2*

Peak Load

~lbs 0

0 2.3

.69

.$45 0

.69

.69 26

15

.39 107

.28

Model 1:

KSG 3717 lb/ inches NSG

.03767 lb sec (inches Model 2::=-KSG

.19439 lb/1nches MSG

.01068 lb - sec2I)nches

GINNA STATION STEAM GENERATOR EVALUATION NRC MEETING APRIL 30, l 982 ANALYSIS AND TESTING PROGRAMS TUBE LOADINGS 1

'LATERAL IMPACT LOADS FLOW-INDUCED YIBRATIONS IC~

0 AXIAL LOADS EXTERNAL PRESSURE THERMAL GROWTH MISMATCHES TUBE SHEET ROTATION AND MISALIGNMENT TUBE DEGRADATION/FAILURE MECHANISMS 0

COLLAPSE e

FATIGUE e

WEAR 0

BURST LABORATORY TESTING 0

COLLAPSE 1

FATIGUE FLOW MODEL

I I INNA STATION STEAM GENERATOR EVALUATION NRC MEETING APRIL 30, 1982 AXIAL LOADS ON PLUGGED TUBES

.SOURCE

~

SECONDARY PRESSURE NO-LOAD SS, P

= 1005 PSIG FULL-LOAD SS, P

= 762 PSIG MAX.

LOAD LB.

-604.

-458.

O'UBE-TO-SHELL INTERACTION HOT STANDBY: TUBE-547 F, SHELL-476 F

-1940.

PLANT LOADING'UBE-517. F, SHELL-547 F

825.

PLANT UNLOADING: TUBE-547 F, SHELL-497 F -1375.

FULL POWER SS:

TUBE-517 F,

SHELL-497 F

-550.

e PLUGGED -TO-ACTIVE TUBE INTERACTION FULL POWER SS T =517 F,

T =565'

~

1410.

NO%'ES'1)

TUBE FREE TO MOVE.*AXIALLYAT TSP (2)

TUBE AXIALLY RESTRAINED AT TSP

STEAM GENERATOR EVALUATION NRC MEETING APRIL 30, 1982 480 N

440 400 360 320

~

1000 LBS TENSILE LCAD r

~

N N

~'

~

.06

~ 04

.G2

02 e

=.Ol 280 240 200 160 120

~ f

~

N

'I

~I' N

~

"875 in. 0.D.x.030>n.

PIALL...

80 aO 0

~ 200 16O 120 s '80

-..:MAX. YIELD STRENGTH ~ 57.7 KSI:,'-'~

'lll. Tl[LN NTINNNTII NN.N Lll:-'-="

GOO LBS:

..-.---'glSILE LQAB'.-..: ':-:.=::.:

" ~~'

' "1

.06 X.04

,02

e

=.01 40 0

.875in O.D.x..g50in.

<A

. MIN. YIELD STRENGTH ~ 35.5 KSI:

~.:...

0 50.:100 150

. 2OO 250 L-.,

300 CONCENTRATED RADIAL LOAD - (LBS)

MAXIMUM STRESS IN TUBES OF VARIOUS OVALITIES LOA"ED WITH 1000 PSI UNIFORM EXTERNAL PRESSURE PLUS CONCENTRATED RADIAL LOAD

~

GINNA STATION' STEAN GENERATOR EYALUATiON NRC MEETING APRIL 30, 1982 7

'.030 WALl.

STRESS (VSI) 3 2

0 0

.2

~ 3

.a,

.5 AXIAL DISTANCE FROM LOAD (IN)

HOOP STRESS IN OUTER FIBER DUE TO 5 POUND RADIAL LOAD

GINNA STATION STEAM GENERATOR EVALUATION NRC MEETING APRIL 30, 1982

SUMMARY

OF COLLAPSE ANALYSIS FOR A NOMINAL 0.050 INCH WALL TUBE WITH 2X OVALITY AND 58 KSI YIELD STRENGTH, A LATERAL LOAD OF 75

.LB. IS REQUIRED FOR INCIPIENT YIELDING.

AXIAL LOAD OF 1000 LB. TENSION REDUCES THE INCIPIENT.

YIELD LOAD BY APPROXIMATELY 10.0 LB.

HOWEVER, THE STRESS FIELD IS HIGHLY LOCALIZED.

TO PRECIPITATE COLLAPSE IT IS, REQUIRED THAT:

1.

THE LOAD BE SIGNIFICANTLY HIGHER IN ORDER TO OBTAIN A THROUGH-MALL PLASTIC ZONE (HINGE)

AND, 2.

THE LOAD MUST ACT AT DIFFERENT TUBE LOCATIONS, IN ORDER TO PLASTICALLY DEFORM AN AREA 2 TO 3 TUBE DIAMETERS LONG AXIALLY.'

GINNA STATION STEAM GENERATOR EVAL'UATION NRC MEETING APRIL 30, 1982

SUMMARY

OF PLUGGED TUBE FATIGUE ANALYSIS DESIGN MIN. WALL =0.045 INCH NOMINAL OVALITY=2%

STRUCTURALLY STABLE TUBES PRINCIPAL LOADING: THERMAL MECHANICAL.DUTY CYCLES (L% CYCLE 'FATIGUE)

CASE LATERAL LOAD IMPACT USAGE FACTOR U

1.

NOMINALLY PLUGGED 2.

NOMINALLY PLUGGED WITH NOTCH NONE NOTCH (SCF=4.0)

. 0.036 0.676 STRUCTURALLY DEGRADED TUBES (LOCALLY COLLAPSED)

. PRINCIPAL LOADING: FLOW-INDUCED VIBRATIONS (CROSS-FLOW TUBBULENCE)

(HIGH CYCLE FATIGUE)

CASE 3.

FIXED-PINNED TUBE SPAN LOCALLY COLLAPSED OVER 2.0 INCH LENGTH NEAR TUBE SHEET LATERAL LOAD LB.

CONTINUOUSLY ACTING 0.

10.

25.

50.

POSTULATED.FAILURE U=l.O TIME, DAYS NO FAILURE 30.

2.5

'.7

SUMMARY

STRUCTURALLY STABLE TUBES HAVE ACCEPTABLE FATIGUE MARGINS STRUCTURALLY DEGRADED TUBE, WHEN CONTINUOUSLY ACTED UPON BY A

)" LATERAL LOAD CAN FAIL IN HIGH CYCLE FATIGUE DUE TO FLUID

~

INTERACTION.

GINNA STATION STEAM GENERATOR EVALUATION NRC MEETING APRIL 30, 1982 WEAR CORRELATION Q

BASIC INCONEL ON INCONEL SPECIFIC WEAR COEFF.

RANGE 58 to 854 IN /lb.

WEAR VOLUME BASED ON RUB AREA

= 8.0" LONG X 0.1 WIDE X 0. 0434" DEEP CONTACT FORCE BASED ON DRAG FORCE ON SEVERED TUBE

= 3.0 LBS.

RUB VELOCITY =

5 in/sec USING ARCHARD THEORY RUB FREQUENCY

=

50 HZ AND MEAN RUB AMPLITUDE

.= 0.050 INCH ESTIMATED TIME RANGE FOR TUBE BURST, 59 DAYS TO 1.27 YEARS 0

CONCLUSIONS FOR THE CASE OF A SEVERED TUBE (AT TUBE SHEET)

RUBBING ON A NEIGHBORING TUBE, CALCULATED FAILURE:

CTIME PERIODS REASONABLY ENVELOP THE OBSERVED WEAR RANGE WEAR BY UNSEVERED TUBE NOT POSSIBLE SINCE FLOW-INDUCED VIBRATION AMPLITUDES ARE SMALL AND WILL NOT RESULT IN TUBE CONTACT

G INNA STATION STEAM GENERATOR EVALUATION NRC MEETING APRIL 30, 1982 BURST CORRELATION MINIMUM TUBE WALL AT BURST ASME CODE NB - 3324.1 P

=

S

= 89.7 KSI Ill U

P

= 780 PSI P.

= 2250 PSI t

= 0.0066 INCH I

MEASUREMENT OF (MINIMUM) WALL OF BURST TUBE (R42 C55).

0.008 INCH

STEAM GENERATOR EVALUATION NRC MEETING APRIL 30, 1982

~Cr ~ SCOICQ2 AIR. ESSED NUT(TYP. 80TH ENDS)

K@ID CAP CAP SCREW 9.0 DIA.'TUSK SWAGKLOK R.O DIA.TKE 0" RINGS (TYP. 80TH EhlD&)

1000 Psl WA'TE'R OR GAS D'YhlAMIC SEAL IMPACT 'ROD STAhlDOF F S LOAD CELL HYDRAULIC CYLINDER.

HYDRAULIC CYLINDE,R MOUNTING FIX'TURE.

I SCHEMATIC-TUBE COLLAPSE TEST

'I 0

'STEAM GENERATOR EYALUATION

. NRC MEETING APRIL 30, 1982 LATERAL LOAD 'BENCH 'TEST-'STATIC IMPACT ROD - TIP.125 x 1.00, 90 TAPER Clamp B3 ock Clamp Block TUBE, O.D.=.872

'.D.=.766" OVALITY= "0"l0 2400 2200 2000 1800 O.D. MIN.

0;D.

MAX.

1600 1400 1200 lD5 1000 800 600 400 200

.872 0

.400

-500

.600

.700

.800

.900 1.00 1.10 1.20 DIAMETER, IN.

GINNA STATION STEAM GENERATOR EVALUATION NRC MEETING APRIL 30, 1982.

'ATERAL LOAD BENCH TEST-STATIC CHISEL.

IMPACTOR TUBE V-BLOCK

-6" V-BLOCK

~

g LOAD (LBS)

OVALITY (X)

SHARP CHISEL, BLUNT CHISEL 0

550 700 0

2;1 0

0..2 0.8 850 1000 3.9 6.0 1.9 3.7 Chisel Face:

Sharp

= 0.030" x 1.0" Blunt = 0.125" x 1.0"

GINNA STATION STEAM GENERATOR EVALUATION NRC MEETING APRIL 30, 1982 DYNAMIC COLL'APSE TESTING O'XTERNAL PRESSURE

=1000'PSI

,0 LATERAL LOAD = 600'LBS 0

IMPACTING SEQUENCE:

a.

IMPACT AT EVERY 1/4" ALONG 0-DEGREE PLANE FROM ONE END OF AREA.TO THE OTHER.

THEN OFFSET 1/8" AND BACKTRACK.

b.

REPEAT STEP "a" ON THE + 20 PLANE c.

REPEAT STEP "b" ON THE -20 PLANE.

1 II 1 II Impacted Area SHARP CHISEL (1.00"x0.030" BLUNT CHISEL (1.00"x0.125")

.SEQUENCE

.NO; INITIAL (INCH)

(INCH) 884/0 86 0.755

0. 724 D MAX/ODMIN ID MIN OVALITY(X)

2. 65 ODMAX/ODMIN (INCH)

/0.873 ID MIN (INCH) 0.766 0.734 VALITY (I)

OX 2

0. 699 0.680

0. 695

0. 664 FINAL 0 928/0 73 0.660 23.5X 0 923/0 76

0. 647 NO COLLAPSE, DEVELOPED CRACK DURING SUBSEQUENT IMPACTS TEST IN PROGRESS AP INCREASED TO 1500 PSI

'OVALIZED IN A VISE

GINNA STAT STEAN GENERATOR EVALUATION NRC MEETING.

APRIL 30, 1982 (C

I FATIGUE TEST

SUMMARY

DE FORMATION SHAPE CONFIGURATION 'XIALTENSION LBS.

AMPLITUDE,INCH FRE(UENCY CYCLES PEAK TO PEAK HZ TESTED RESULTS FLAT 2"

LONG.

FIXED-SUPPORTED 0.

.05

.07

.09

.12

.16

.20

.25

.30

.40

.50

.3 x 10 (EACH LEVEL) 39.3 3.6 x 10 NO FAILURE FLAT 2"

LONG FIXED-FIXED 1000.

.05

.30 63.6 2x10 NO FAILURE FLAT 2"

LONG FIXED-FIXED, NOTCHED AT TRANS-ITION t

1000.

.30 63.6

.9 x 10

.FAILED -

NOT AT NOTCH KIDNEY-SHAPED 1"

LONG KIDNEY-SHAPED 2"

LONG FIXED-FIXED FIXED-FIXED, LATERALLY. IMPACTED 1000.

1000.

.30 67.7 6x10 NO FAILURE

GI NNA.STATION STEAM GENERATOR 'EVALUATION NRC MEETING APRIL 30, 1982 MODEL TEST OBJECTIVES NATURE AND EXTENT FOREIGN OBJECT MOBILITY MAGNITUDE FOREIGN OBJECT IMPACT LOADS STABILITY CHARACTERISTICS OF DEGRADED TUBES NATURE AND EXTENT OF TUBE-TO-TUBE INTERACTION

WRAPPER SUPPORT

. WITH WED%5 PATCH PLATE GINNA STATION (TEAN GENERATOR EVALUATION NRC MEETING APRIL 30, 1982

~SMELL TUBE LANE.

WRAPPER PATCH PLATE ROW 45

~

L234 SQUARE PITCH XYP.

WRAPPER.

S UPPOR T WITH vfEDGES

~ W TUBES (as 5 O.D.)

ROW 44 ROW 45 0

0 0

0 0'.

0 0

-8 COL.46.

COL.

8 COL. 50 OUTL INE OF TEST GEOMETRY 7I/

~ I

~ +a

/

I//

~'/

0 0

0 0 0

/

COL.52 4

PLUG WELD

.'687 DIA. '

Cl RCULATION HOLES' 62

~I

'I

G INNA STATION STEAM GENERATOR EVALUATION NRC MEETING APRIL 30,,1 982 0

1st Support Plate

.Perforate Exit Plat 56 66" 2.'00

.810

32. 38" ube

'1.00" Section View of 71ow Test Model

G INHA STATION

'TEAM GENERATOR EVALUATION NRC MEETING APRIL 30, 1982 MODEL TEST COHCLUS IONS OBJECT MOTION RANDOM IN NATURE AND OCCURRED FOR

'LL ORIENTATIONS AND POSITIONS MAXIMUM FOREIGN OBJECT IMPACT FORCES ACCELEROMETER DATA 120 180 LBS.

FORCE TRANSDUCERS 200 - 350 LBS.

TUBES WITH UNDEGRADED AHD LOCALLY DEGRADED CROSS SECTIONS WERE STABLE SEVERED TUBE TENDED TO NESTLE BETWEEN NEIGHBORING TUBES AHD INTERMITTENT IMPACTS WERE OBSERVED

GINNA STATION STEAM GENERATOR EVALUATION NRC MEETING APRIL 30, 1982 CONCLUSIONS COLLAPSE

-SIGNIFICANT LEVELS OF COLD WORK FOUND ON COLLAPSED TUBING SURFACE

-LARGE FOREIGN OBJECT REMOVED FROM STEAM GENERATOR CAPABLE Of.

PROVIDING 100 - 350 LBS.

IMPACT LOADS

-LATERAL,IMPACT LOADS IN THE RANGE OF 50.,-

75 LBS.

WILL IN COMBINATION WITH A1000, PSI EXTERNAL PRESSURE CAUSE INCIPIENT YIELDING FATIGUE

-STRUCTURALLY DEGRADED TUBE CAN FAIL DUE TO HIGH CYCLE FATIGUE WHEN SUBJECTED TO CONTINUING LATERAL IMPACT LOADS

-STRUCTURALLY DEGRADED TUBE WILL NOT FAIL DUE TO FLUID INDUCED VIBRATION

=-NOMINAL PLUGGED TUBE WITH A NOTCH OR STRESS RISER WILL. NOT FAIL IN FATIGUE.

-FATIGUE TYPE STRIATIONS FOUND AT FAILED TUBING SURFACES WEAR

\\

-TUBE WEAR PATTERNS COMPATIBLE WITH ONE TUBE RUBBING AGAINST ANOTHER

-SUFICIENT WEAR CAN OCCUR TO CAUSE BURSTING OF A TUBE

-EDDY CURRENT DATA SUBSEQUENT TO FEBRUARY 1979 CONSISTENT WITH

'I

, PROPAGATION OF DEGRADATION BY WEAR PROCESS BURST

-LABORATORY EXAMINATION INDICATED A PURELY DUCTILE FAILURE R42 C55

-CALCULATED AND OBSERVED BURST THICKNESS ARE CONSISTENT

GINNA STATION, STEAM GENERATOR EVALUATION NRC MEETING APRIL 30, 1982 REPAIR PROGRAM o

ACCESS HOLES o

TUBE REMOVAL o

TUBE PULL o

LOOSE PARTS o

MECHANICAL PLUG REMOVAL o

INSPECTIONS AND TESTS o

RADIATION EXPOSURE

GINNA STATION STEAN GENERATOR EVALUATION NRC NEETING

'-APRIL 30, 1982 ACCESS HOLE LOCATION L'aDqF S

suvpopz wl Wta F

Q'/ALL

~

t 0

~ GINNA STATION

. STEAM GENERATOR EVALUATION NRC MEETING APRIL 30, 1982 A

SS HOLE

.SHELL NO.

4.WEDGE AREA WEDGE WRAPPER w t~r

~ c>

~ <

000 0 0 0

ROW 45 44 0

0 0 t ~

IP 0 0 0

000 0

0 0 0 000 0 0 42 OOOO 0

0 0 0

0 0 0 0 40 COLUMN 62 61

)

. 60 59 58 57 56 55 54 55 52 PLOD PPLEG REMOVED/PLUGGED'EFECT/

PLUGGED PULLED PLUGGED 51 50 49 48 47 46 45 BURST/ REtIltGVED/PLUGGED NO DEFECT/ PLUGGED O ACTIVE

/l

GINNA STATION STEAN GENERATOR EVALUATION NRC NEETING APRIL 30, 1982 ACCESS HOLE COVER

/

l COVE 2 PL47E

, GINNA STATION STEAM GENERATOR EVALUATION NRC MEETING APRIL 30, 1982 NO.. 6 WEDGE AREA SHELL Oi 0 0 0 WRAPPER I

RON 25-.

rj'2.

~ j

~

I I

I

+

i ACCESS HOLE Goo y

~

5

~

8

'l l7 -!

.0

~ 0 ooo GGO 0

0, 3:

l

'-l6~

WEDGE N

7v/I

/I

,/I/I II II Ii Il

/s 0

+000 GGO 0 0 0

000 OOOO 0 0 0

X I 9

t 8

7 \\

0 0 0 0,0 6 --"

~.

5 --.

9'2 '..9I

. 90 99...8 6

5 COLUMN

GINNA STATION STEAM GENERATOR EVALUATION NRC MEETING APRIL 30, 1982 RADIATION EXPOSURE o

PREPARATION 40 Man rem Vq o

PRE-REPAIR INSPECTIONS 80 o

ACCESS HOLES 30 o

TUBE REMOVAL o

=-

TUBE PULL 50 o

LOOSE PARTS REMOVAL 40 o

MECHANICAL PLUG REMOVAL 20 o

POST-REPAIR INSPECTIONS o

CLOSEOUT 25 15 TOTAL 335 Man rem RGE-11

GINNA STATION STEAM GENERATOR EVALUATION NRC MEETING APRIL 30, 1982 TECHNICAL BASIS REPAIR PROGRAM 0

ACCESS PO.RTS

~

THERMAL/HYDRAULIC EVALUATION

~

STRUCTURAL EVALUATION

.,FATIGUE COLLAPSE GEOMETRIC STABILITY

GINNA STATION STEAM GENERATOR EYALUATION

. NRC MEETING APRIL 30,

'l982 I

vA I

bh ~Th.

/ ~ %>t5>

I X

~ Location of Access Ports

GINNA STATION STEAM GENERATOR EVALUATION NRC MEETING APRIL 30, 1982 STRESS

SUMMARY

FOR 3 INCH DIAMETER ACCESS PORT Ratio-of Maximum Stress to Alliable-Stress'oad.Condition Design Normal and Abnormal Test Fatigue Usage Factor Bolt Replacement Interval Bolt 0.63(1).

0.65(1)

O.gS(2) 0,65(1) 0.62(2) 0.85(4)

S years Cover 0.29(3)

(1.0 0.29(3).

0.00 Shell (6) 1.O1(5)

(6) 0.16 Notes:

(1).

Avera'ge Service Stress (2)

Maximum Service Stress

'3)

Primary Membrane Plus Bending (4)

Fatigue usage factor based on specified replacement interval (5)

Acceptable per Code.

A simplified elastic - plastic analysis was invoked for the fatigue evaluation.

(6), Primary stress limits ai e satisfied by Code rules for opening not requiring reinforcement.

GINNA STATION STEAM GENERATOR EVALUATION NRC MEETING APRIL 30, 19S2 THERMAL HYDRAULIC EVALUATION PURPOSE DETERMINE FLUID YELOC ITIES FOR'SE IN EYALUATING FLUID-INDUCED LOADS METHODS CHARM ANALYSIS

.MEGAN ANALYSIS First Suppo Plate 51.81" ri 5 ~

~o*

r r

+rto

~

~ ~ 0 g

>a

~ 0

~ ~

4e

%0

~ ~

6.5" q,o< 5Ad CPA

~ yP

~ rP

~leo r

~

~+a

~ ~

p+ ~ ~

Ot 4

~tre 0

~ opt io

~

~ oi

~\\ye ~ ~

~o

~ +

~yr

~

VN a

~4

~

2.14 ft/sec through Mrapper Opening Chare hnalysis Plane

~ 2.38 ft/s~

Through Mrapper Opening 20 Tube Sheet Tubes Plugged 30 MECAN hydraulic Analysis

I 1

GINNA STATION STEAM GENERATOR EVALUATION NRC MEETING APRIL'30; 1982 BETWEEN-TUBE CROSSFLOW VELOCITIES 'IN AND NEAR THE TUBES REMOVED REGION Eocation Crossflow Velocity Crossflow Velocity Crossflow Velocity (1 block of 2 blocks of

~

- nominal....

tubes removed

- tubes. removed Perimeter Cell (Face A)

~

Perimeter Cell (Face C)

Perimeter Cel 1 (Face B)

~

One Cell in from Perimeter (Face B)

Two Ce'lls in from P erimeter (Face B) 8.2 ft/sec 8.2 ft/sec 9.01 ft/sec 8.54 ft/sec 8.21 ft/sec 9.13 ft/sec 9.13 ft/sec 10.12 ft/sec 9.48 ft/sec 9.16 ft/sec 9.13 ft/sec 9.13 ft/sec 10.33-ft/sec 10.95 ft/sec 10.46 ft/sec U

c B

Node 11 A

C c

-- ~ Case

~ --

4 Nominal UA

'MAXIMUM TUBE GAP VELOCITIES WITH AND WITHOUT TUBE REHOVAL Maximum Gap Velocit; ft/sec 9.01 One block of tubes removed 10.12 Two blbck of tubes removed 10.95

GINNA STATION STEAM GENERATOR EVALUATION NRC MEETING APRIL 30, 1982

SUMMARY

'OF TURBULENCE ANALYSES FIXED-FIXED BOUNDARIES CROSS-FLOW VELOCITY, 10.0 FT/SEC DAMPING RATIO,'.01 CROSS SECTION OF DISTORTED ZONE CYLINDER (NOMINAL) 10 PERCENT OVALITY KIDNEY VIBRATION AMPLITUDES 'MILS~

TVRBUL'ENCE

0. 81

0. 83 0.83

G I NNA STATION STEAM GENERATOR EVALUATION NRC MEETING APRIL 30, 1982 FATIGUE THERMAL MECHANICAL LOADS NOMINAL PLUGGED TUBE

.036 USAGES 1

~ 0

.NOMINAL PLUGGED TUBE WITH NOTCH OR STRESS RISER

.676 USAGE+1.0 HYDRAULIC LOADS STABILITY CROSS FLOW TURBULENCE (10 FT/SEC, NOTCH, F-P) 10.12 FT/SEC Q 14 FT/SEC

+11.24 KSI~13 KSI AT 10ll

GINNA STATION STEAM GENERATOR EVALUATION NRC MEETING APRIL 30, 1982 COLLAPSE 5

N K.

0 tazamD

. O 3t16" THINNED LENNH D 35" THINNED lKNGTH o 3l4"THIRD LENGTH

+ )-)IZ'HINNED/ENGTH D

29 40 40 No 1tO NAXIMlHDECRADATION, % <<oil COLLAPSE PRESSURE OF UNIFORMLY THINNED TUBING" 4

TESTING RESULTS

-COLLAPSE STRENGTH NOMINAL TUBE 5000 PSI

-80$

UNIFORM THINNING FOR COLLAPSE AT 1020 PSI 4

FOR A GIVEN.X WALL DEGRADATION COLLAPSE PRESSURE FOR LOCALIZED THINNING WILL BE GREATER THAN FOR UNIFORM.

THINNING 4

TUBES IN STEAM GENERATOR HAVE PASSED A

PROOF COLLAPSE TEST

GINNA STATION STEAM GENERATOR EVALUATION NRC MEETING APRIL 30, 1982 GEOMETRIC STABILITY PRESSURE THERMAL LATERAL TUBE DEFLECTION BROKEN HOT LEG OF

,TUBE GUIDED BY UPPER PLATES TUBE SEVERED JUST BELOW THE FIRST PLATE TSP THK ~ 0.75 INCH 51.88 INCH Schematic of a Partial Tube

GINNA STATION STEAM GENERATOR EVALUATION NRC MEETING APRIL 30, 1982

SUMMARY

o 'AUSE OF TUBE RUPTURE o

WORK IN PROGRESS o

LOOSE PARTS MONITORING SYSTEM o

ADEQUACY OF REPAIRS o

INTERMEDIATE OUTAGE

~..'INNA STATION STEAM GENERATOR EVALUATION NRC MEETING APRIL 30, 1982 POSTULATED FAILURE MECHANISM SE UENCE Mechanical i oad Active Tube Tube Plugged Collapse Vibration Shredding Sever Wear Plugged Tube Wear Active Tube Plugging Burst

GINNA STATION STEAM GENERATOR EVALUATION NRC MEETING APRIL 30, 1982 LOOSE PARTS MONITOR SENSOR LOCATIONS

~ HOT LEG COLD LEG 2

I TUBE RKET

Ql

ML17256A932

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