ML20071A003

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Forwards Results of Inservice Insp of Steam Generator Tubes, Per Surveillance Requirement 4.4.4.5(b)
ML20071A003
Person / Time
Site: San Onofre Southern California Edison icon.png
Issue date: 04/04/1991
From: Krieger R
SOUTHERN CALIFORNIA EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9104150146
Download: ML20071A003 (11)
v • d • e


Text

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,e gypp" Southem Califomia Edison Company

$ AN ONOFHU NUCLE AR GENERATING STATION P. O,13OX 128 SAN CLEMENTE, C ALIFORNIA 92674 J120 N.W.MRIEGER TELEPHONE STAtlON MANAGER (714) an0 4?55 April 4, 1991 U. S. Nuclear Regulatory Commission Document Control Desk Washington, D. C. 20555 Subj0ct:

Docket No. 50-362 Special Report Inservice Inspection of Steam Generator Tubes San Onofre Nuclear Generating Station, Unit 3

References:

A.

PWR Steam Generator Examination Guidelines, Revision 2 Electric Power Research Institute (EPRI) Report Number NP-6201, dated December 1988.

B.

Letter from M. O. Medford (SCE) to Mr. G. W. Knighton (USNRC) dated April 5, 1985.

C.

Licensee Event Report Number 3-90-005.

Pursuant to Surveillance Requirement 4.4.4.5(b) of Appendix A, Technical Specification to facility Operating License D F-15, this report is being submitted to the Commission following the completion of Nervice inspection of steam generator tubes at San Onofre Unit 3.

Eddy _ current inspection of the steam generator tubing was completed on May 7, 1990. A total of 4191 tubes (23% of the tubes in service) in two steam generators were inspected full lcngth and 34 tubes were removed from service by mechanical plugging.

This inspection significantly exceeded the amount of tubing required to be inspected per Surveillance Requirements 4.4.4.0 through 4.4.4.2 including all prospective C-2 expansions [i.e., a 3% sample plus a 6%

(2S)'and a 12% (4S) expansion in each steam generator).

The planned inspection programs for both steam generators were fully

. consistent with recent industry recommendations in the "PWR Steam Generator Examination Guidelines" (Reference A).

The programs included inspection of the full length of 100% of the tubing in the area of the tube bundle where the batwing wear mechanism previously described in Reference B is active.

The programs included tubes adjacent to tie rods where denting was anticipated based on experience with the San Onofre Unit 2 steam generators in October 1989.

The programs also included general surveillance of the full length of 20% of the remainder of the tubing.

The programs were expanded to include tubes adjacent to, or associated with tubes exhibiting new eddy current indications.

Ohlr W/ ens %f s\\

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7.

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~ Document Control Desk '

In steam generator E-088, 2106 tubes-were inspected.

No tubes were found to

.be defective.- Eight tubes were preventively plugged due to wear mechanism-

~

previously described in Reference B.

In addition, three tubes at the tube buadle periphery were preventively plugged due to degradation at diagonal strap supports.

In steam generator-E-089, 2085 tubes were inspected.

One tube was found to be defective _ at-its intersection with a vertical-strap support and was plugged.

.Two tubes were preventively plugged due to the wear mechanism described-in Reference B, three tubes were preventively plugged due to degradation at vertical strap supports, and one tube was preventively plugged due to tie-rod denting

~ Fifteen-tubes were preventively plugged and staked and one tube was preventively plugged in response to the failure of the feedwater sparger reported in Reference C.

As required by. Surveillance Requirement 4.4.4.5(b), complete results of the recently completed inservice inspection of steam generator tubing are provided

.in the enclosures. Enclosure 1 provides the steam generator internal location reference guide.

Enclosures 2 and 4 provide a list of eddy current testing

-indications, including tube identification, indication depth and the axial-location of-the indication in the tube.

Enclosures 3 and 5 provide-a list of tubes. plugged after completion of the inservice inspection.

If you require any additional information, please so advise.

Sincerely, Li

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e Enclosures.

J._B.. Martin.(Regional Administrator, USNRC Region V) cc:.

C. W -CaldwellL (USNRC. Senior Resident--Inspector, Units 1, 2 & 3)

.'t.. Kokajko (Project Manager, SONGS 2/3, USNRC, ERR)

Institute of Nuclear Power Generation'(INP0) 4

Page 1 Of 2 CE MODEL 3410 TUBE SUPPORT DRAWING VH2 VGM VC2 VH1 VH3 VC3 VCt 1

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Page 2 of 2 CLARIFICATION OF TVBING/ SUPPORT INTERFACES AB0VE THE 7TH FULL EGGCRATE SUPPORT R0WfS)

JJBING/ SUPPORT INTERFACES 0

0 V3 C

BC 84-114 08H 09H DBH

'VH2.VH3 VSM.VC3 VC2 DBC 09C.08C 83 08H DBH VH2.VH3.VSM.VC3.VC2 DjC 08C 51-82 08H DBH~

VBl VSM.VC3 DBC 08C 49-50 08H DBH VSM DBC 08C 19-48 DBH VSM DBC 1

1-18 DBH DBC s

[-

1 Enclonure 2 CUMUIATIVE REPORT 04/90, SOUTilERN CALIFORNIA EDISON, SAN ONOFRE, UNIT 3 STEAM CENERATOR: 88 PACE:

1 0F 3

,_' ?, LOCATION: ALL DATE:

05/22/90 CRITERIA: On TO 100%

TIME:

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CONAH NUCLEAR, INC.

r CUMU!ATIVE REPORT 04/90, SOUTHERN CALIFORNI A EDISON, SAN ONOFP.E. UNIT 3 STEAM CENERATOR: 88 PACE:

2 0F 3

^

LOCATION: ALL DATE:

05/22/90

~

CRITERIA: On-TO 100%

TIME:

13:48:07 l

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EXAM 12 TENT _ l

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CONAM NUCLEAR, INC.

CUNULATIVE REPORT 04/90, SOUTHERN CALIFORNIA EDISON, S AN ONOFRE, UNIT 3 STEAM CENERATOR: 88 PACE:

3 0F 3

LOCATION
ALL DATE:

05/22/90 CRITERIA: 0% TO 100%

TIME:

13:48:07 l-l l

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EX E EXTENT l

l l

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l ROW l COL lIlEAT# l LEC l PROGRAH j ACTUAL l REH j REEL l PROBE l 14 CATION l VOLTS jMILlDECl % lCHl 142 I54l l 6~ TEC TEH TEC TElll j 052l580VL DBH+

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1._. I NUMBER OF TUBES SELECTED FROM CURRENT OUTAGE:

85 i

NO TREND ANALYSIS REQUESTED i

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C0 HAM NUCLEAR, INC.

LIST OF. TUBES PLUGGED San Onofre Unit 3 Steam Generator E-088 E2M Column Reason 82 16 Preventive Maintenance 48:

86 Preventive Maintenance 34 104 Preventive Maintenance 83 17 Preventive Maintenance 50 86 Preventive Maintenance 34 74 Preventive Maintenance 47 97 Preventive Maintenance 147 81 Preventive Maintenance 49

=97 Preventive Maintenance 46 86 Preventive-Maintenance

/

49 99 Preventive Maintenance i

k.

6

CUMULATIVE REPORT

)

04/90, SOUTilERN CALIFORNIA EDISON, SAN ONOFRE, UNIT 3 STEAM CENERATOR: 89 PACE:

1 0F 2

"( LOCATION: ALL DATE:

06/01/90 CRITERIA: 0% TO 100g TIMEl 10:03.09 l

l l

l l

EXAM EXTENT l

l l

l l

CURRENT l

l ROW l COL l HEAT # l LEG l PROGRAH l ACTUAL ] REM l R EEL l PROBE ]

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2.2

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l __ _ l l._, l i

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..f CONAM NUCLEAR, INC.

CUMULATIVE PR>OR'l 04/90, SOUTilERN CALIFORNIA EDISON, SAN ONOFRE, UNIT 3 STEAM CENERATOR: 89 PAGE:

2 0F 2

~'

'y LOCATION: ALL DATE:

06/01/90 CRITERIA: On TO 1004 TIME:

10:03:09

~

l l

l l

l EXAM EXTENT l l

l l

l CURRENT l

I ROV l COL l!!EATn [ LEC l PROGRAH l ACTUAL l REH l REEL l PROBE j LOCATION lVOLTSjHILlDECl t lCill l142 IO8l 11 TEll DBil TEll DBil 047 580VL TSil+

3.1 1.0 UD fi2

[115l111l l C lTEC TElllTEC TEll) l 018 580VLlVil3 -

1.27 l

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0.9l l 0l<20l181 l 43l131l l C lTEC TElllTEC TElli l 031 580ULlVSM- 0.78 l

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[

0.51 l

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1.5l l

0l 26l18]

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0.6l 1134l 341 1l l 46l138l l C lTEC TElllTEC TElll l 031l$80ULl04C. 0.17 l

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0l 21l18l

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l 032l580ULlVSH+ 0.84 l

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0l 27l18l l _. l._ I I

I I

_I I

I I

_l-1 I

I 1._.l NUMBER OF' TUBES SELECTED FROM CURRENT OUTAGE:

51 NO TREND ANALYSIS REQUESTED

-)

.N CONAM NUCLEAR, INC.

,oo LIST OF TUBES PLUGGED San Onofre Unit 3 Steam Generator E 089 Rag Column Reason 104 28 Preventive Maintenance 46 102 52% Indication at Location VSM 0.69 51 95 Preventive Maintenance 43 105 Preventive Maintenance 40 100 Preventive Maintenance 41 101 Preventive Maintenance 44 102 Preventive Maintenance 143 107 Preventive Maintenance 141 109 Preventive Maintenance 141 107 Preventive Maintenance

.142 110 Preventive-Maintenance 142 108 Preventive Maintenance 140 110 Preventive Maintenance 140 108 Preventive Maintenance 2

8 Preventive Maintenance 143 109 Preventive Maintenance 1

9 Preventive-Maintenance 1

3 Preventive Maintenance 2

4 Preventive Maintenance 1

5 Preventive Maintenance 2

6 Preventive Maintenance 1

7 Preventive Maintenance 141 111 Preventive Maintenance l

1

-

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