ML20107B378

Inservice Insp Rept for 841023-1104.On 841021,Unit 1 Began Shutting Down Due to primary-to-secondary Steam Generator Tube Leakage.Westinghouse Provided Necessary Eddy Current Exams & Tube Plugging Svcs

ML20107B378
Person / Time
Site:	Prairie Island
Issue date:	01/08/1985
From:	Mary Anderson, Dahlman L NORTHERN STATES POWER CO.
To:
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ML20107B369	List: ML20107B378
References
NUDOCS 8502200370
Download: ML20107B378 (40)

Text

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i PRAIRIEISLAND NUCLEAR GENERATING PLANT Red Wing, Minnesota UNITS 1 AND 2 t

4 I

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anseeNE APOL45 e 57. PAUL "Ne $Y$= t i

INSERVICE INSPECTION - EXAMIrlATION

SUMMARY

PRAIRIE ISLAND NUCLEAR GENERATING PLANT - UNIT I OCTOBER 23 to NOVEMBER 4, 1984 STEAM GEilERATOR TUBE - EDDY CURRENT EXAMINATInN INSPECTI0fl PERIOD 3 1

1l BM' SSS5 !SSShga y o NORTHERN STATES POWER COMPANY l

MINNEAPOL!S. M!NNESOTA REPORT DATE: January 8, 1985 C0hWERCIAL SERVICE DATE: DECEMoER 16, 1973

h5P M

. PRAIRIEISLAND NUCLEAR GENERATING PLANT Red Wing, Minnesota UNITS 1 ANO 2 l

24NNE APOLl1 e ST. PAUL

. "'0'u'?!'A*d.

INSERVICE INSPECTION - EXAMIt!ATION

SUMMARY

PRAIRIE ISLAND NUCLEAR GENERATING PLANT - UNIT I OCTOBER 23 to NOVEMBER 4, 1984 STEAM GENERATOR TUBE - EDDY CURRENT EXAMINATInN INSPECTI0fl PERIOD 3 NORTHERN STATES POWER COMPANY MINNEAPOLIS, MINNESOTA REPORT DATE: January 8, 1985 COMMERCIAL SERVICE DATE: DECEM9ER 16,1973

NORTHERN STATES POWER l 1

l i

l INSERVICE INSPECTION - EXAMINATION

SUMMARY

FOR THE PRAIRIE ISLAND NUCLEAR GENERATING PLANT - UNIT I OCTOBER 23 to NOVEMBER 4, 1984 INSPECTION PERIOD 3 STEAM GENERATOR TUBE - EDDY CURRENT EXAMINATION Commerical Service Date: 12-16-73 Prepared by: M . Anderson M&SP Engineer L. Dahlman M&SP Specialist Report Date: 1-8-85 Reviewed by: , dm-

~G Krause, Supt.

Materials & Spec.Pr.

Apptcved by: .

D Youngdahl, Manager Prod. Plant Maint.

. MLA113084WMH01-LT Page 1 of 6

i I

NORTHERN STATES POWER COMPANY PRAIRIE ISLAND NUCLEAR GENERATING PLANT - UNIT I

-INDEX-1.0 Introduction

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2.0 Summary 3.0 Examination Method 4.0 Equipment and Materials 5.0 Personnel 6.0 Examination Results Appendix A -

Table I - Personnel Table II - Procedure Listing Table III - Equipment and Materials Appendix B - Steam Generator No.11 Eddy Current Examination Results and Tube Sheet Maps Appendix C - Steam Generator No. 12 Eddy Current Examination Results and Tube Sheet Maps Appendix D - Form NIS-1, Owners Data Report for Inservice Inspection Attachment I - NRC Committment Reference MLA113084WMH01-LT Page 2 of 6

INSERVICE INSPECTION EXAMINATION

SUMMARY

l FOR THE l PRAIRIE ISLAND NUCLEAR GENERATING PLANT UNIT I OCTOBER 23 to NOVEMBER 4, 1984

'~

1.0 Introduction This report is a summary of the steam generator tube eddy current examinations performed on steam generators No.11 and 12 at Prairie Island-Unit I. The examinations were performed during the period from October 23 through November 4,1984 after tube leakage was detected via secondary side chemical analysis. Prairie Island-Unit I began commercial operation on December 16, 1973.

2.0 Sunnary On October 21, 1984, Prairie Island Unit 1 began shutting down due to primary-to-secondary steam generator tube leakage of approximately 0.33 gpm which escalated to approximately 0.65 gpm before hot shut-down conditions were ~chieved.

a (Technical Specifications of 1.0 gpm were not exceeded.) Westinghouse was mobilized to provide necessary eddy current examinations and tube plugging services. What follows is a synopsis of the relevant events which occurred during the brief outage period defined previously.

Primary man-ways were removed on October 23, 1984, and visual inspections of both hot and cold leg tubesheets were performed in steam generators #11 and *12 with secondary side hydrostatic pressures exceeding 600 psi. A small leak (approximately one drop per second) was observed in the cold leg of steam generator #11 (row 25, column 87). No visible leakage was observed in steam generator #12 at this time.

Multifrequency eddy current examinations were performed in steam generator

1. 11 on row 25, column 87, and approximately 25 surrounding tubes. These examinations were conducted for the full length of each tube with standard Zetec MIZ-12 Data Acquisition equipment. The analysis of this data showed that the defect in tube #R25 C87 was located at the seventh tube support plate, cold leg. Analysis of the data for the surrounding tubes indicated that, while some tube degradation at locations other than the seventh tube support plate were observed, no other defective tubing in this sample was evident.

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On October 24, 1984, a second tubesheet visual inspection was conducted on steam generator #12 while under secondary atmospheric head pressure only and an extrenely small leak (approximately one drop every three minutes) was observed in the hot leg, row 17, column 42. An eddy current examination was perfonned on this tube and the defective area was determined to be in the hot leg tubesheet region (beginning at the top of the roll transition extending to approximately 15 inches above the tube end). This defective area exhibited multiple, discrete tube wall penetrations exceeding the technical specifications plugging limit.

MLA113084WMH01-LT Page 3 of 6

The following tubGs were mechanically plugged based on visual leakage and/or eddy current examinations:

Location S/G-#11 of Defect R25 C87 #7 Tube Support Plate - Cold Leg R7 C94 Tubesheet - Cold Leg (Previous Committment)*

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Location S/G-#12 of Defect R17 C42 R13 CIS Tubesheet - Hot Tubesheet - Hot LegLeg (Previous Comittment)*

R6 C93 Tubesheet - Cold Leg (Previous Comittment)*

• Note: See Attachment #1 for details of this committment.

After Unit I returned to power, on October 28, 1984, another tube leak was detected by plant chemistry personnel in steam generator #12. Before the plant could get shut-down this leak had grown to approximately 3.5 gpm.

Steam generator #11 exhibited minimum leakage per plant chemistry, therefore a Technical Specification, C-1 type sampling program was devised for steam generator #12 only. This sample included all tubes with previously reported tube wall degradations ( 20%),plus approximately 300 tubes in the region of the tube bundle where tube wall degradations were historically prevalent. Westinghouse performed the ET inspection of this sample which consisted of full length tube examinations utilizing standard Zetec MIZ-12 Data Acquisition equipment. The data analysis was perfomed by Conam Inspection using Zetec digital analysis (DDA-4) equipment.

On October 31, 1984, a visual inspection of the hot and cold leg tubesheets were performed on S/G #12 and a relatively large leak was evident (small continuous stream) in the hot leg, row 18, column 45. This tube was eddy current examined and the results exhibited a defective area of approximately ten inches in length, starting at about six inches above the tube end and extending to about sixteen inches above the tube end, hot leg (tubesheet crevice region). Again, this area consisted of multiple, large tube wall penetrations with the largest observed at approximately ten inches above the tube end.

When this infomation became available, NSP initiated an inspection which consisted of the hot leg tubesheet region up to the first tube support plate for approximately 100% of all S/G #12 tubing (26 tubes were not l "

inspected; these tubes were inaccessible due to positioning fixture and template plugs). These exciinations were performed in addition to the C-1 sampling which was previously discussed. Also, a special larger diameter

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(0.740 inch) probe was used in the tubesheet region examinations which improved sensitivity by minimizing probe wobble. The tubesheet region

, inspection resulted in the detection of one (1) additional tube (row 9, column 26) which exhibited an indication located just above the roll transition area (approximately 4.8 inches from tube end), hot leg.

, Although this indication was of a very small amplitude (1.36 volts),

l its phase suggested it to be in excess of the plugging limit ( 50%

tube wall penetration) and was consequently plugged.

l MLA113084WMH01-LT Page 4 of 6

The following tub:s in S/G #12 wsre mechanically plugg:d based on visual leakage, eddy current examinations, or for preventative measures:

Tube Number Defect Location / Severity Comments R18 C45 Tubesheet - Hot Leg /100% Observed Leak Visually R9 C26 Tubesheet - Hot Leg /92%

R37 C75 First Tube Support Plate

- Cold Leg /46% Preventative R34 C78 First Tube Support Plate

- Cold Leg /42% Preventative Prairie Island - Unit I is scheduled for its ninth refueling outage to tentatively begin on January 5, 1985. During this time NSP will conduct eddy current examinations on 100% of the tubing in steam generators No.11

& 12. In addition to full-length tube examinations, an extensive investigation of the tubing in the hot-leg (inlet), tubesheet crevice region for both generators shall be performed.

3.0 Examination Method As previously stated,' Westinghouse was contracted to perform the eddy current examinations utilizing a Zetec MIZ-12 data acquisition system.

This system provides multi-frequency capabilities for use in determining tube integrity. The frequencies utilized for each examination were 400 KHz and 100 KHz in the differential mode, with 210 KHz and 100 KHz in the absolute mode.

' Analysts from Zetec and Conam were utilized to evaluate the examination data. All data was subjected to 100% re-evaluation (2nd level review) before the final results were tabulated. Analysis was performed using digital evaluation equipment (DDA-4) which provides an increase in analytical capability.

4.0 Equipment and Materials All equipment used in the examinations are listed by either serial number or type, as applicable, along with their respective calibration dates in Table III of Appendix A.

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5.0 Personnel ,

' Northern States Power Company contracted Westinghouse to perform the examinations, with Zetec and Conam providing technical / analytical support.

Hartford Steam Boiler Inspection and Insurance Company, representing ANI, provided the Authorized Inspection. .

All personnel involved in the performance or evaluation of examinations are listed, along with their title, organization and ASNT certification level, in Table I of Appendix A. Certification for examination personnel are maintained on File by Northern States Power Company.

MLA113084WMH01-LT Page 5 of 6

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6.0 Examination Results A sumary of the tubes exhibiting eddy current indications is included in the cummulative listing of indications found in Appendices B and C for steam generators #11 and #12, respectively. The total numbers of tubes plugged to date are also exhibited in these appendices.

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- MLA113084WMH01-LT Page 6 of 6

APPENDIX A TABLE I - PERSONNEL TABLE II - PROCEDURE LISTING TABLE Ill - EQUIPMENT AND MATERIALS l

O l

MLA121384WMH01-LT i

! NORTHERN STATES POWER COMPANY APPENDIX A TABLE I PERSONNEL LISTING PAGE1 of 1 EXAMINER TITLE ORGANIZATION UT P T VT ET RT BEHARY, G.T. TECHNICIAN W II) I BURGESS, W.A. TECHNICIAN W II JENKINS, G.P. TECHNICIAN W II POLLICE, R.A. C0ORDINATOR W II PFARR, T.A. TECHNICIAN W II t

BRONSON, J.I. TECHNICIAN W I

- HAZEN, R.P. TECHNICIAN W II HOSELY, R. COORDINATOR W I ROSSI, W. TECHNICIAN W I TOMMARELLO, D. TECHNICIAN W II 4

GILBERT, B.F. EVALUATOR ZETEC(2) IIA SIEGEL, J.D. EVALUATOR ZETEC IIA CHAMBERS, D.M. EVALUATOR CONAM(3) IIA LOFGREN, R. EVALUATOR CONAM IIA MARLOW, R.E. EVALUATOR CONAM III ANDERSON, M.T. M&SP ENGINEER NSP DAHLMAN, L.C. M&SP SPECIALIS1 NSP HUGHES, R. ANII HARTFORD STEAM BOILER INSPEC-TION AND INSURANCE CO.

. FOOTNOTES: (1) ORGANIZATION (1) Westinhouse Electric Corporation Nuclear Services Division P.O. Box 2728

. Pittsbu'rgh, PA 15230 (2) ZETEC P.O. Box 140 Issaquah, WA 98027 (3) Conam Inspection 660 South 31st Street Richmond, CA 94804 MTA113084WMH01

1 NORTHERN STATES POWER COMPANY APPENDIX A PRAIRIE ISLAND UNIT II TABLE II PROCEDURE LISTING PAGE 1 of 1 PROCEDURE NUMBER FIELD PLANT. APPROVAL FIELD CHANGE PROCEDURE TITLE CHANGE DESCRIPTION

.AND REVISION CHANGE DATE REMARKS MRS 2.4.2 NONE Multi-Frequency Eddy 10-23-84 NONE Gen - 23, Rev. 5 Current Inspection of with Generic Steam Generator Tubing -

Change #1 Preservice and Inservice MTA112884WMH01

NORTHERN STATES POWER COMPANY A APPENDIX TABLE 111 EQUIPMENT AND MATERIALS PAGE1 0F d MATERIAL OR TYPE OR CALIBRATION EQUIPMENT SERIAL NUMBER R BATCH REMARKS BrushRecorder(s) S/N 0533 8-3-84 01307 9-10-84 01308 9-12-84 0644 8-2-84 0025 7-5-84 30365 9-11-84 TapeRecorder(s) S/N 2105A01653 9-24-84 HP 3968A2 2105A01491 7-11-84 00947 6-8-84 00946 7-30-84 0681 8-3-84 30230 7-27-84 0999 9-17-84 30246 6-8-84 s

MIZ-12 Main Frame S/N 30250 10-21-84 0682 5-29-84 0557 9-27-84 Freq. Plug-In S/N 0561 6-7-84 -

0684 6-1-84 0552 6-7-84 0558 6-4-84 30247 10-22-84 0636 6-7-84 00890 10-20-84 0584 6-4-84 0575 9-27-84 0568 9-27-84 0638 6-26-84 0709 9-28-84 0923 8-9-84 00877 6-19-84 MIZ-12 Mixer S/N 0579 6-7-84 Plug-In 0640 6-4-84 0563 6-7-84 0571 6-4-84 0666 9-26-84 01627 9-28-84 0562 6-26-84 00881 6-21-84 0597 9-19-84 0598 6-8-84

i

-l j NORTHERN STATES POWER COMPANY APPENDIX A f TABLE III

EQUIPMENT AND MATERIALS PAGE 2 0F 2 MATERIAL OR TYPE OR CALIBRATION

! EQUIPMENT SERIAL NUMBER DATE OR BATCH REMARKS NUMBER MIZ-12 Display S/N 0266 8-6-84 Module / Scope 0006 6-11-84 0698 10-21-84 1

i '

0151 6-14-84 0537 9-11-84 0268 7-13-84 1

00923 7-13-84 30240 8-7-84 1 00918 8-6-84 0556 9-25-84

-Vector Analyzer S/N 00942 7-3-84 00938 9-19-84 Calibration Stan- WEM 02660 AVB Standard dards Inconel 600 Z- 1411 Defect Standar i

} Z- 1341 ABS Standard 4 WEM 02680 AVB Standard j Z- 1399 ABS Standard i Z- 1429 Defect Standar 1 i

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i APPENDlX B i

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DEC St. 1944 PRAIRIE ISLAND NUCLEAR CENERATING PLANT LIST OF PLUGGED STEAM CENERATOR TUSES 1 ----------------------- __ --__ .....----------------------------------------.------.. ........------.......

l CEN SIDE ROW COL YEAR RENARKG/CONNENTS

, NO.

! 11 OUTLET .36 48 8' - AVB 52 4 - AVB 37 54 4 - AVB

! 76 4:1- S/1

, 38 SS $ - AVB l 54 s - AVB 57 4: t- s/t 39 56 3-S/2 42 31 -

40 :l- S/t 43 50 - AVB l 57 8 - AVB i.

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DEC 31. 1984 PRAIRIT ISLAND NUCLEAR GENERATING PLANT LIST OF Ir1 PERFECT. DEGRADED. AND OEFECTIVE TUBES _

~ ~ ~ ~ ~ ~ ~

N-~ REbkRkb/bbbbkNTh~

~

bEb~~~bibk~~~kbb~ cot. YEAR Fit ON' TO 2FkbT~

NO. 1R OBS

- - - - - - - - - - - - - - - - - - - - - - - - - - = - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - = = = = - - - - - - - - - - - - - - - - - -

11 INLET 2 1 79- 5 " ABOVE TUBE SH T 'NNING <20 83- 58 "" ABOVE TUBE SF T NNING <20 3 1 79- 5 AEOVE TUBE S T NN NG 65 4 1 79- 35 " ABOVE TUBE S T NH NG 100 6 19 53- IST SUP T NN NG 39 7 3 83- 5 " ABOVE TUBE SH T NH NG <20 10 13 SS- IST SUP T NH NG 32 26 SS- 2ND SUP T NH NG 26 12 16 82-  : ST SUP T NN NG 33 77 43- '.ST SUP T NH NG 24 13 6 82- ~ST SUP T NN NG <20 83- SUP T NN NG <20 79 SS- -.GT ST SUP T NN NG <20 4 42- 1

" ABOVE UBE SH T HH NG <20 156 25 33- d>T SUP T Nb NG <20 42 s2- 4T SUP T Nb NG 24 83- 47 SUP Hb HG 23 45 83- 2ND SUP Hb NG 24 75 SS- IST GUP NH NG <20

'85 82- 2ND SUP T NH NG 21 83- 2ND SUP T HH NG 20 17 4 82- 1 ABOVE TUBE SH T NH NG 21 83- IST SUP T NN NG <20 5 82- 1 ABOVE UBE SH 2 " ABOVE T HH NG <20 83 82- ',ST SUP T NH NG <20 83- .ST SUP T NN NG 20 18 45 43= WND SUP T HN NG <20 67 43- IST SUP T NN NG <20 19 28 83- 2ND SUP T NN NG 26 47 al- 25 " ABOVE TH SUP T NH NG 90 81 83- ST SUP T NH NG <20 20 24 83- ST SUP T NH NG 33 43 82- 4 "

ABOVE 7TH SUP T NN NG 81 83- IST SUP T NH NG <20 86 84- 2ND SUP T NH NG <20 21 43 82- 4 " ABOVE ?TH SUP T NN NG 85 84- SUP T NN NG <20 88 84- '.ST ST SUP T NN NG <20 22 74 (3- ST SUP T NN NG 24 80 a3- ST SUP T NN NG <20 81 83= aST SUP T NN NG 22 23 in 83- IST SUP T NN NG <20 24 31 82- 3RD SUP T NN NG BELON 79 82- IST GUP T NN NG <20 83- 1 ST SUP T HH NG <20 25 43 83- UND SUP T NH NG 27 i

51 83- 19" BELON U BE SH T NN NG 43 62 82- ST SUP T NN NG <20 79 83= ST SUP T NN. NG <20 81 83- ST SUP T NH NG 32 26 39 83- !ND AVB T NN NG <20 83= 3RD AVB T NN NG 20 56 82- 3RD AVB T NN NG <20 83- 3RD AVB T NH NG 23 82- 4TH AVB T HN NG <20 83- 4TH AVB T NH NG 32 63 82- ST SUP T NH NG 22 83= ST SUP T .NN NG <20 g 27 31 82- .57 SUP T NH NG <20 W 83- ST SUP T NN NG NG

<20 d3 39 83- .ST AVB T NN 21 0 82- 2ND AVB T NH NG 24 83- 2HO AVB T NNING 28

== 83- 3RD AVB T NNING 22 q IST AVB T NN HG <20 l

, 61 82-NN NG 32 83- IST AVB T 1

0 82- 2NO AVB T NN HG <20 th 83- 2ND AVB T NNING 20 83- 3RD AVB T NNING 22 g 65 82- 3RD AVB T NNING <20 29 46 82- IST AVB T Nt LNG <20 N 83- IST AVB T NiING 21 82- 2ND AVB T Nt I Nrt <20 43- 2NO AVB T NNING 36 82- 3RD AVB T .NNING <20

o , *

• in DEG 31. 1984 PRAIRIE ISLAND NUCLEAR CENERATING PLANT 1.15T DF I f1P E A F E CT . DEGRADED. AND DEFECTIVE TUBES GEN Elbk RbU bbl YEAi! kRbb kb b kkb7 N ~ reb RkS/bbbbENTh~

NO. O OSS

- - - - - - - - - - - - - - - - - - - - - - - - _ _ - . - - _ _ _ - - - - - - - - _ - - - - - - - - - - - - - - - - - - - = = = = = _ _._=------ - - - - - - - - = _ . - - - - _ - = - - - - - - . . . - - - -

II INLET 29 46 8: 1- SRD AVE T ' NN NG 36 4: 1- 4TH AVB T NN NG 24 50 9;;I- 4TH AVB T NN NG <20 54 s -

2ND AVB T NN NG <20 g-a.g- 2ND AVB T NN NG "6 57 OND AVB T N4 NG $3 SS- 2ND AVB T Ni4 NG 43 82- 3RD AVB T Nh NG <geS SS- 3RD AVB T Nb NG SS- 4TH AVB T Nb NG 21 62 42- ST SUP T Nb NG <20 30 53 43- ST AVB T NH NG 21 82- ND AVB 3RD AVB T NN NG <20 3 2ND AVB' NNING 24 59

$g-e 8.-

SRD AVB NN NG 31

}GT AVB AVB NN NG <20 q-- .ND T NN NG <20 s 3RD AVB T NH NG <20 4 - 4TH AVB NN NG 28 41 42- IST SUP H NN NG <20 43- IST SUP H NN NG <20 65 82- 2ND AVE TH N NG <20 SS- 2ND AVB T N NG 24 31 47 43- AVB T N NG <20 83- $RD ND AVB T NN NG 20 55 42- SRD AVB T NN NG <20 SS- 3RD AVB TH NN NG 32 83- 4TH AVB TH NH NG 22 56 S- }ST TH NN NG 22 4.g- .ND AVBAVB TH NN NG <20 43= 2ND AVB TH NH NG 35 42- 3RD AVB TH NN NG <30 43- 3RD AVB TH NN NG 43 4TH AVB TH HN NG <20 12 4TH AVB TH NN NG 36 59 43- IST AVB T 4 NN NG <20 83- 2ND AVB T 4 NH NG 32 +

S3- 3RD AVB 1 NN NG 35 83- 4TH AVB i NH NG 40 60 42- IST AVB 4 NH NG <20 3- 2ND AVB T4 NN NG 25 22- 3RD AVB T4 NH NG <20 SS- . 3RD AVB T4 NNING 29 83- 4TH AVB T4 NNING 26 32 41 92- ST SUP T4 NNING <20 m3- ST SUP T4 NN NG 31 53 42- ND AVB T4 NN NG 26 SS- 2ND AVB T4 NN NG 33 42- 3RD AVB T4 NN NG 32 83- 3RD AVB T4 NN NG 40 56 83- IST AVB T4 HNING 20 SS- 2ND AVB T4 NNING 21 41 SS- 2ND AVB T4 NNING 20 33 64 3- 3RD AVB T4 NNING 21 34 35 38 37 (3-e 83-3RD AVB 2ND AVB T4 NNING NNING (20

<20 Ti 38 43- IST SUP 7i NNING 32 D 40 83- IST AVB T4 NNING 23 D 43- 2ND AVB T4 NN NG 33 42 83- IST AVB T4 NN NG 23 LQ 42- 2ND AVB T4 NH NG <20 tj SS- 2ND AVB T4 NNING 31 48 43- 3RD AVB T .NNING <20 OD

== 42- 4TH AVB T NNING 24 SS- 4TH AVB T NPING 33 51 83- 3RD AVB T' N ING <20 0 43- 4TH AVB T- N ING <20 m 57 SS- 2ND AVB T- NH NG 21 42- 3RD AVB T NN NG <20 SS- 3RD AVB T4 NN NG 33 pa 58 $3- 4TH AVB T NN NG 31 y 36 38 a3- 2ND AVB T NN NG <20 SS- 3RD AVB T NN NG 21 47 SS- 3RD AVB T4 NN NG 20 82- 4TH AVB T 4..NN. NG <20 Y

.a i.asT"E@*7E! sees $U D E dDED?' U E*Dl"scN OU'TuSes _

~~5is-- EiDi non cot. veAF

~~~~~~Fi5s----~~~~~ 76--~~~~~~-- EFEET-~~~~-/-~~iisisii c5Artisis'

..N.D.--------- R OBS 11 INLET 36 47 SS- 4TH AVB T Nb NG 23 51 S2- 3RD AVB T Nb NG <24 83- 3RD AVB T Nb NG 23 54 42= 2ND AVS T Nb NG <20 SS- 2ND AVS T Nb NG 31 83- 3RD AVB T Nb ING <20 83- 4TH AVB T NNING <20 56 42- CND AVB T 54NING <20 43- 2ND AVB T NN NG 33 42- 4T AVS T NH NG <20 53- 4T AVB T NN NG 38 57 43- 47 AVS T N NG <20 40 SS- 2ND AVB T N NG 26 j 61 82- 2ND AVB T N NG < 0 43- *ND AV8 Y NH NG 9 82- 3RD Ava T Nb NG < 0 SRD AVB T Nb NG 25 63 2- 3RD AVS T Nb NG <20 13-3- 3RD AVB 3RD AVB T Nb NG <20

$2- T NbING <20 53- 3RD AVB T NNING 21 37 46 82- 3RD AVS T NN HG (20 83- SRD AVB T NN NG <20 56 SS- 2ND AVB T NN NG 27 61 42- 3RD AVS T NH NG <20 83- 3RD AVB T NN NG 20 38 50 43- 3RD AVB T NN NG <20 51 92- 3RD AVB T NN NG <20 m3- 3RD AVS T NN NG 27 52 42- 3RD AVB T NN NG <20 43- 3RD AVB T NN NG 24 53 SS- 2ND AVB T NN HG <20 42- 3RD AVE T NN NG <20 SS- SRD AVB T NN NG 31 43- 4TH AVB T NNING 20 57 42- IST AVB T NNING 36 43- IST AVS T NNING 48 42- 2ND AVB T NH NG 33 43- 2ND AVB T NN NG 42 83- 3RD AVS T NH NG 29 58 43- }ST AVB AVS T NH NG 22 83- .ND T NN NG <20 3 42- 3RD AVB T< NN NG <20 2

3- :lRD AVB T< NN NG 25 39 35 3- EST AVB T. NNING 22 S6 2- ST AVS T- NN NG <20 43- ST AVB T< NN NG <20 42= '

ND AVB T< NN NG 24 83- 2ND AVB T' NN,NG 41

, 82- 4TH AVB T -

NN}NG <20 a

83- 4TH AVE T -

NN NG 29 57 83- 4TH AVB T -

NN'NG 20 54 42- 2ND AVB T -

NN NG <20 43- 2ND AVB T- NH NG 20 82- 3RD AVB T .i NN NG <20 43- 3RD AVB T4 NNING 23 82- 4TH AV8 T4 NN NG (20 43- 4TH AVB T .4 NH NG 27 9 40 32 83- 3RD SUP T .4 NN NG 20 m 41 83- IST AVB T .4 NN NG 26 q 43- 2ND AVS T .i NN NG 25 0 52 83- 2ND AVB T4 NH NG <20 83- 3RD AVB Ti NN NG 24

- 43- 4TH AVB T .] NN NG 23 O 56 42- 4TH Ava T4 NN NG <20 83- 4TH AVB T4 NN NG 32 0 59 82- 2ND AVR T4 NN NG <20 th 43- 2ND AVB Tj NH NG 30 82- 3RD AVB T' NN NG <20 43- 3RD AVB T 'si NH NG 30 g 32- 4TH AV8 T NN NG 25 M 43- 4TH AVB T 'i1 NN NG 34 61 82- 2ND AVE T4 N NG <20 43- 2ND AVS T4 N NG 20 42- 3RD AVB T 'i N NG <20

o e '

• DEC 31, 1984 PRAIRIE ISLAND NUCLEAR GENERATING PLANT LIST OF INPERFECT. DEGRADED. AND DEFECTIVE TUBES ==

_______-__ ....--_-____--_-- ___.____=_-_----------_ _ _ _ _ _ _ . - - = - _ _ _ _ _ __= -=- __--.=___ _____- __ _ _ _ _ = = = _ _ _ _ _ - - _ _

GEN SIDE RON COL YEAR TO 1EFECT  % REMARKS / COMMENTS

__N_D_._

_ -___ _---_______ --_____------- FROM --_ ____--____ ._---_-__-----------.R--_BS___ 4 O

_ - - _ = _ _ _ _ - - - - - - _ - _ _ _ _ - - - _ - -

11 INLET 40 61 SS- 3RD AVB T1'NNING 24 41 3a 43- 3RD AVB T1 NN NG <20 i l3- 4TH AVB T1 NN NG <20 99 i l - 3RD AVB 4TH AVB Ti NN HG <20 i l - 3RD AVB T4 NH NG 24 a l - 4TH AVB T4 NN NG 20

, 49 J L2- 3RD AVB T4 NN NG <20 i

al3- 3RD AVB T4 NH NG 25 a l2- 4TH AVB T4 NN NG <20 43- 4TH AVE T4 NN NG 26 50 SS- IST AVB 4 Nb NG <20 42- 2ND AVB 4 Nb NG <20 S= OND AVE 51 56 I2-s-

3RD AVB 3RD AVB T1 4 Nb Nt NG NG 24

<20 T1 Nb NG 20 in - 4TH AVE Ti Nh NG 26 58 i l - OND AVB Tf NN HG 37 i l - 3RD AVB 1i NH NG <20 59 i l - 3RD AVB T4 NN NG <20 a l - 3RD AVE Tt NN NG 48 42 54 a l - 3RD AVB T4 HN NG <20

$- 3RD AVB T NN NG 27 s- 4TH AVB T NH NG <20 4 - 4T AVB T NH NG 28 43 31 $ - 67 SUP T NN NG 39 e - 3R AVB Ti NN NG <20 4 - 3RD AVB T4 NH NG 25 e- 4TH AVB T4 NN NG 20 49 4 - 3RD AVB T4 NN NG <20 3RD AVB T4 t4N NG 32 t$=- 4TH AVB T4 NH NG 28 51 3- 3RD AVB T4 NN NG 27 i 3- 4TH AVB T4 NN NG 22 52 2- 3RD AVB T1 NN NG <20 3- 3RD AVE T1 NN NG <20 53 12- 3RD AVS Ts NN NG <20 SS- 3RD AVB T4 NN HG 22 43- 4TH AVE T4 NH NG 20 55 83- 2ND AVB T4 NH NG 21 42- 3RD AVB T4 NN HG <20 83- 3RD AVE 74 NN NG 23 82- 4TH AVB T4 NN NG <20 83- " 4TH AVB T4 HNING 28 58 43- I ABOVE TUBE SH T4 NNING <20 60 43- 2ND AVB T4 NHING 20 44 49 2- 4TH AVE 7i NNING <20 53 -

ST SUP T4 NN HG <20 61 -

ST SUP Ti NH NG <20 62 8 - ST SUP T4 NH NG <20 46 43 82- 3RD AVB T(INN NG (20 45 82- 2ND AVB TtlHNING (20 46 82- 3RD AVB TIINNING <20 OUTLET 7 3 82- 5 " ABOVE TUBE Sr T4 NNING 20 81- 5 " ABOVE TUBE S- T4 NNING 23 94 44- 15" BELON TUBE 5 -

T4 NN NG 99 8 4 8 -

5 " ABOVE TUBE S -

T4 NH NG 40 9 3 4 -

5 " ABOVE TUBE S -

T4 NH NG 40 8 -

12 " ABOVE TUBE S 11 NN NG 37 g 16 20 68 89 4

8 25 " ABOVE PTH SUP" T4 NH NG 89 ST SUP N

4 21 SS 4'-

44-3- ST SUP ST SUP 7i NN NG T (INN HG

<20 23 O 22 86 80-T NNING 38 ST SUP T NNING 35

$1- ST SUP T NNING Al g 87 83-84-ST SUP T4 NH NG <20 C3 ST SUP T4 NN NG 26 88 84- ST GUP T4 NN NG 43 23 87 84- ST SUP T4 NN NG 38 O es a4- ST SUP T4 NH NG 33 m 24 3 82- :lRD SUP T4 NH NG

$ 44- ST SUP T4 NH NG 34 8 43- ST SUP T4 NN NG 28 H 84- ST SWP T4 NH NG 38 N 25 84 43- IST SUP T4 NN NG 35 85 42- IST AVB T4 NN NG 32

= v i e

DEC 31, 1984 PRAIRIE ISLAND NUCLEAR GENERATTNG PLANT LIST OF IMPERFECT, DEGRADED, AND OEFECTIVE TUBES .-m

~

bkN h5DE ROW CO kkkR 3RbH Tb bkFkb7 /. kkMkRKS/COAAEbTh' NO. OR OBS

--~~-------------------------------------------------------

---

=-----

11 OUTLET 25 as as- -----------

IST S UP TH NN'NG 43 87 44- 77H SUP T NN NG >90 26 56 4'.- 4TH AVB T NH NG <20 27 61 4. - IST AVB T NN NG <20 45 8' - 3RO AVB TH NH NG <20 85 8:1- IST SUP TH NH NG 23 84-- IST SUP T NN NG 35 29 43 4 - 2ND AVB T HN NG 38 46 8 IST AVB T NH NG <20 8 - 2ND AVB T NH NG <20

- 3540 AVB TH NN NG <20 57 - 2ND AVB TH NH NG <20 80 1'

S; l-3RO AVB IST SUP T4 T 4 NN NN NG NG

<20 20 81 l l: 1- aST SUP T 4 NH NG (20 43 1 i: l- 2NO SUP T 4 Nb NG 23 30 43 I l

- IST AVB T4 Nb NG <20 el - 2ND AVB TH Nb NG 54 4 .- 3RD AVB TH Nb NG <20 4 .- 4TH AVB T NN NG <20 53 4 .- IST AVB T NN NG <20 4 -- 2ND AVB T NN NG <20 4 - 3RD AVB T N ING <20 45 8 2ND AVB T NFING <20 79 4:)- IST SUP TH N ING 21 31 43 4 =- 2ND AVB TH NNING <20 4 3RD AVE TH NNING St A ,- 4TH AVB T NNING 33 44 8 - - IST AVB T NH NG <20 4 2ND AVE T NN HG 36 8 - - 3RD AVB TH NH NG 32 54 a 2ND AVB TH NN NG 52 8 - 3RD AVB TH NH NG 36 8 - 4TH AVB TH NH NG <20 55 - 3RD AVB T NN NG <20

$ .- 2ND AVB T NN NG <20 56 e NH NG <20 4 .- 3RD AVB Tl 8 - 4TH AVB TH NN HG <20 59 s - 4TH AVB T- NN NG <20 60 4 - 3RD AVB T -

NN HG <20 61 8 .- 2ND AVB T -

NNING <20 a .- 3RD AVB T -

NH NG 37 78 4:n- IST SUP T -

NH NG (20 80 83- 2ND SUP T -

NN NG 29 32 41 8'.- }BT SUP T4 NH NG <20 45 s' -- .NO AVB TH NH NG <20 4 - 3RO AVB TH NH NG 41 53 4 - 2ND AVB TH NN HG <20 s 3RD AVB TH HN NG <20 77 8:1- IST SUP TH NN NG 28 79 a3- IST SUP TH NN NG 54 83- 2HO SUP TH NN NG 44 34 76 83- ST SUP T NN NG 29 78 83- ST SUP T NN NG 25 79 8 - NO SUP T NNING 45 35 42 8 .- IST AVB TH HN NG <20 8 - ONO AVE TH NN NG <20 44 8 .- 4TH AVE TH NN NC <20 62 8.- 4TH AVB TH HN NG 49 eg 2ND SUP TH NN 'NG 34 78 80-- TH NN 'NG N 8l 2ND SUP 45 Q 36 35 8 - IST AVB TH NN :NG <20 0 8 - 2ND AVB TH NNING 56

= 4 .- 3RD AVB TH NNING 56 g

- 4TH AVB TH NNING <20 40 - IST AVB TH NN NG 52 H - 2ND AVB THINN NG 67 8 - 3RD AVB THINN NG 54 O a - - 4TH AvB TH HN NG 52 47 8 4TH AVB TH HN NG <20 m 48 $ -- 2ND AVB TH NN NG 42

.. S 3RD AVB TH NN NG 42 52 8 - 2ND AVB TH NN NG 49 H 54 4 .- 2ND AVB TH NNING <20 M 56 S..- 2ND AVB TH.NNING <20

a = r .

DEC 31, 1984 LIST PRAIRIE OF IMPEAFECT, ISLAND NUCLEAR DEGRADED, GENERATING AND DEFECTIVE PLANT TUBES

--_----_----__.___--__...---__-..-------------______=----------------_.---______..

GEN SIDE ROW COL YEAR FHOM TO DEFECT  % REMARKS / COMMENTS NO.

-- - - - - - --- . = = - . = = - - - - --

--- - _ __--__-- - - - - - - -- ---_O_R_ OSS _ --- _ - _ - - - - - - - - - - _ _ . - .

43 .- 3RD AVB T ' NN NG <20

&& 4 -

3RD AVB T NN NG <20 37 46 4 .- SRD AVB T N NG <20 4 -

3RD AVB T NG 54

& l

'l- IST SUP NG 49 34 8 -

4TH AVB Nt NG 34 52 $ -

3RD AVB H NH NG <20 '

54 s -

2ND AVB TH NN NG <20 8 -

3RD AVB T NN NG 63 4TH AVB T Nb ING 60 57 s -

IST AVB T Nh LNG <20 8 -

2ND AVB T4 Nb NG <20 39 54 4 =

IST AVB T NF NG <20 8 .- 2ND AVB T Nh NG <20 54 4 .- 2ND AVB T Nb NG (20

$ .- 3RD AVB TH NN NG <20 s -

4TH AVB TH NN HG <20 40 56 8 -

4TH AVB TH NN NG <20 59 8 -

3RD AVB TH NNING <20 4 -

4TH AVB TH NNING <?O 42 28 ll- 3RD SUP TH NN NG <20 31  != 3RD SUP TH NN NG 34 40 3- 3RD SUP TH NN NG 45 62 42- ST SUP TH NH NG <20 43- ST SUP TH NN NG <20 4 - ST SUP TH NN NC <20 43 49 S :lRD AVB TH' NN 11 4 <20 8 -

4TH AVB TH NN NG <20 i

50 4 -

3RD AVB TH NH NG 39 St- 4TH AVB TH NH NG <20 i 54 SS- IST SUP TH NH NG <20 55 8 4TH AVB i

4 57 8 8

2ND AVB 3RD AVB TH TH NN NN NG NG (20 56 el SS-3RD SUP TH NN NG <20 44 TH NN NG 24 i $3 83- IST SUP TH NN NG 23 45 37 42_ 3RD SUP TH NN NG <20 SS- 3RD SUP T -

NN NG <20 40 43- 3RD SUP T -

NH NG <20 49 43- ST SUP T -

NN NG 23 50 SS- ST SUP T -

NH NG 23 51 SS- ST SUP T NN NG 34 53 $3- ST SUP T NN NG <20 SS e3- .ST SUP T NN NG 22 59 43- 3RD SUP THINN NG 34 P

46 43 41- 2ND AVB THINN NG <20 l

l m

9 4

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M

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4 i,

i APPENDIX C i

STEAM GENERATOR NO.12 j EDDY CURRENT EXAMINATION RESULTS AND TUBE

.i SHEET MAPS i,

3 4

i i

i i

l i r f

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MLA121384WMH01-LT

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'. .id DEC 31. 1984 PR TRIE ISLANO NUCLEAR CENERATING PLANT L ST OF PLUGGED STEAM GENERATOR TUREG

~~~ ~~ ~~~~~~~~~~ =~~~~~~~'

side

~~ ~ ~~

cEN ROn COL YEAS ~~~ RinAsis~c6ssEsis NO.

---

_=---- --__ _________. - -_ _ - _ - _ _ _ _ _ _ _ - _ ____ _____=== =_____________ _ _ _ _ _ _ _ _ _ _ _ _ . . _ .

12 INLET I 29 43-34 03-34 43-42 03-2 4 St- 5/O 23 SS-3 34 SS-4 93 44- S/O 4 49 S3-9 4 44-3 5 84-6 9 43-7 42 S4-4 45 44-32 35 1- 5/O 34 78 4- S/O 36 2 3-37 5 4- 5/O OUTLET 1 9 43- S/

34 43- S/

36 43- S/

42 43- 5/

2 6 41-El SS- S/I 3 38 83- S/I 6 93 84-3 49 43- 5/

v 26 54- S/

13 IS 84- S/

16 59 43- S/

17 42 44- 6/

IS 45 44- 5/

32 35 SI- AVI L 34 74 44-36 42 43- S/I 37 75 44-l

! n2 W

, u3 I O i

O l

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DEC 31, 1984 PRAIRIE ISLAND NUCLEAR GENERATING PLANT LIST OF IMPERFECT. DEGRADEO. ANO DEFECTIVE TURES --

__ _ . . = = _ .

GEN NO.

SIDE ROW COL YEAR _ _ _ _ - -FROrt

_ - ._ . _ . . . . . . . . . . . . . .TO. . . . . . . . . . . .DEFECT Y.

_ 12

_ = _ = _ _._ = ....._ ____=_.__ _.......... ._ . _ . ._ _

INLET 1 29 83- 12" BELOW TUBE

__=_..O.R.O.BS..........RENARKS/CONMENTS

'NN NG 98 li 62 f*:

8 -  ::: ilL8018tl

." BELOW TUB Tg i U" N8 98 S SOUIRREL u RREL 1 82- IST SUP TN HN HG <20 2 1 SS- 11" BELOW TUSE SH 2ND SUP T NN NG POSSIBLE BEND 3 4 42- }& "

ABOVE 4TH SUP T NN NG ISO 83- 47 "

4POVE 4TH SUP T NN NG <20 38 TH NN NG <20 4 49 SS-43- 11" BELON TUBE SH TH NN NG <20 SOUIRREL 83 SS- 10" BELOW TUBE SH TH NN NG <20 SOUIRREL 9 26 84- 16" BELOW '4TH 'UBESUPSH TH NH NG <20 Il 77 82- ST SUP TH NN.NG 92 SS- ST SUP TH NNING <20 O 82- 1:NO SUP T NNING <20 S 44- 12" BELOW TUBE SH T NN NG <20 l3' 5 4 78- NO SUP T T

NN NG NN NG <20 86 82- (ND SUP TH NN NG <20 Sg- 2ND SUP TH NH NG <20 l' !I 24: If:: ilt8d TU*i RN IN NN N8 '88 49 42- 2ND AVB TH NH NG 83- 2ND AVB <20 82= TH NN NG 28 SS- 3RO AVB TH NN NG <20 44 82-3RD AVB TH NH NG <20 ST AVB TH NN NG <20 77 82-82-

}ND

. AVB TH NN NG <20 ST SUP TH NN NG <20 43- ST SUP T NN le 45 44- NG <20 84- 10" BELOW U8E SH 11" BELOW TUBE SH T NN NG 100 49 42- ONO AVB T NN: NG 108 83- TH NNING <20 42= 2NO AVB TH NHING 22 3RD AVB TH NNING (20 83- 3RD AVB TH NN'N3 20 77 42- IST SUP TH 43- IST SUP NN e4G <20 42 83= 2ND SUP TH NH NC 24 19 33 SS- ST TH NH NG 20 83- }ND AVB TH NH NG <20

. AVB fH NN NG <20 77 42- SUP TH NN NG 20 64 82- ST SUP (20 43- T"NO TH NN NG <20 IST SUP TH NN NG 26 82- 2ND SUP TH NN NG <20 83 83- 2ND SUP TH 21 82 83- IST SUP NN NG <20 22 47 (3- TH NH NG 28 64 s2-2NO AVB TH HH NG 22 42- IST SUP TH NH NG <20 2NO SUP TH NN NG <20 SS 83- 2ND SUP TH 24 64 S2= ST SUP TH NN NG (20 2S 68 82- NN NG <20 83-ST AVE T NN NG (20 26 ST AVB T NN NG 24

'O 65 42- ST SUP T 29 21 82- 2 " ABOVE TUSE SH TH NN NG <20 W S3- 3 "" ABOVE TUBE SH NNING <20 4 84- 3 TH NN:NG <20 y 82 44- ABOVE JST SUP sST SUP TH NN ' NG 22 44- TH HN NG 29 30 49 42- }ST SUP TH NH NG 29 m 32 79 44-2" BELOW sST AVR TH NH NG <20 2NO SuP TH NH NG <20 33 76 44- 3RD SUP T .NN NG 0 79 44- 3RD SUP <20 m = 34 74 44- 3RD SUP T INNING <20 35 76 44- 2ND SUP T INNING <20 34 62 43- TH 'NN :NG <20 CD 38 47 43-TUBE SH TH HN NG 44 39 S7 2ND AVB TH NH 64G 22 43- 4TH AVB TH NN NG <20 41 35 43- 4TH AVE TH NN NG <20 50 42- 3RD AVB TH NH NG (20 43- 3RD AVB TH NN NG 22 43 59 42- IST SUP TH NN NG <20 62 42- IST SUP TH NN NG <20 43- IST SUP THINN NG (20 OUTLET 6 93 44- 19" BELOW TUBE SH THINN NG 75

6 0 a 0 LIST O $t1kE N kh D D C W TURES -

GEN SIDE ROW COL YEAR FROM TO EFECT Y. REMARKS

__N_O_.______________________________________________________________________ R

_ __ _ O S_S___ ________ _ _ _ __ _ _/ COM M 12 OUTLET 13 91 3- ST SUP T NH NC 22 4- ST SUP T NN NG 3$

17 49 4- NO AVE T NN NG 24 44- RD AVS NN NG (20 94 43- .ST SUP H NH NG 24 44- .ST SUP H NN NG 24 IS 49 S4- .ST AVS TH HP NG 20 44-  ; NO AVE T Nt NG 2 19 33 $4- j':87 AVS T N NG (2 e4- NO AVR

N NG <2 4- 3RD AVS

HG <24 4- 4TH AVS '

H-4 N NG NG *0 22 47 4- 3RD AVE <30 4 $4- IST SUP '

N NG 23 23 7 54- jRO SUP T -

NN NC 39 24 5 84- <N AVE T <

NN NG <20 4 42- S SUP 7 -

NN NG < 0 43- 8 SUP T -

Nt. NG <.0 84- 87 SUP T -

Nb NG <20 86 83- ST SUP T -

Nb NG (20 44- ST SUP T -

Nb NG 23 25 48 84- ST AVS T -

NH NG El 77 44- USE SH T -

NH NG <20 84 44- ST SUP 1 -

NN NG <20 46 43- ST GUP T -

NN HG 20 84- ST SUP T NN NG 30 26 77 44- UBE SH T .4 NN NG <20 7 4- USE SH T 4 titi HG <20

$ 4- ST SUP T 4 NH NG <20 27 e

• ST SUP T NH NG 37X e5-

- ST .uP T -

NH NG 29 84- ST .UP T Nil NG 3 24 to 4 l' = ST" ' .UP T -.

HP NG (.0 4:1- S "

.UP T -

NP NG <ge li- S L3P T -

N NG <*O

- S' ' '

T -

NH NG <20

<>- S .UP

-UP T -

NH NC 25 29 42 $3- S'"

,UP T u NN NG 24 43 53- 8 >UP T - NH NG <20

$4- S" SUP T - NH NG <20 39 21 7 -

28 " ASOVE .ST SUP T i NH NG <20 33 e6 4- ST SUP 7 i NH NG <20 s - ST SuP T 4 NN HG *5 44-e -

ST SUP T 4 N NG 38 32 35 L' N O AVS T >i NP NG 49 4 - 3RD AVS T- Nt NG 31 34 77 4:i- ST SUP TF NN 1G 24

$<,- ST SUP TF NN 4G 38 78 42- ST SUP TF NH 1G 30X (3- .S SUP T- NH 1G 32 a4- S SUP T -

NH NG 42 35 7e 84- '

SUP 36 74 $3- S SUP S

T T- NH NH NG NG [5 64 54- S' SUP TH NN NG 31 75 S SUP

$3- i NH NG (20 S SUP e4- -

4 NN HG <20 76 42- ST SuP '

i Nk NG <20 D 43- ST SUP '

4 Nb NG 34 e4- ST SUP T -Q Nb NG 39 D8 37 71 83- ST SUP T 4 Nk NC 25 tQ 44- ST UP f i Nb NG <20 0 73 43- ST UP T 4 Nb HG 24 44- ST UP T4 Nb NG 23 N

= 75 43- ST UP TH HH NG 25 84- ST SUP T4 NH NG 46 38 44 44- .ST AVS T 4 NN NG 22 0 44- :lHO AVE 7 4 NN t, G <20 et 66 e4- ST SUP

NN bG 33 et SS- ST SUP '

NN 0G <20

• 44- ST ' iUP '

NN t< G 22 72 43- ST ' UP H t NG <20 44- ST ' lUP TH NG *0 39 48 42-43-ST 'UP TH NG <3X 3

ST 'UP TH NH NG 3a 84-  :.ST ,UP TH NN.NG 37

47 a a .

DEC 31. 1984 PRAIRIE ISLAND NUCLEAR GENERATING PLANT LIST OF IMPERFECT. DEGRADED. AND DEFECTIVE TUBES

~ ~ ~

CEN SkDE ROW COL ~~5EER ~ FRUN TO UEFECT '/. kbHkRKh[CObMbHTS~

NO O

_ . _ _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ . _ ___ _ _ . = _ _ _ _ _ .__ .R_O_B_S

_ _ _ = _ _ _ _ = = . . . _ _ _ _ _ _ . . . . .

OUTLET _____ __29 12 40 82- 4TH SuP__ _ _ _ _ _ 7TH SUP T) Nb NG_. 20 BETWEEN 8 - 37 "" ABOVE 6TH SUP Tb No NG <20 8 - 39 ABOVE 6TH SUP T6 Nk NG 22 48 4 - ST SUP T Nb NG <20 14- ST SUP TI Nb HG 23 41 35 4- TH AVB T6 Nk NG <24 50 84- 3RD AVB T Nb NG <24 42 57 43- 34 " ABOVE 3RD SUP T NH NG <20 82- 18" BELOW 4TH SUP. T NN NG <20 60 43- IST SUP T NN NG <20 43 42 83- IST SUP T NN NG <20 44 60 43- ST SUP T NH NG 23 84- ST SUP T6 NN NG 25 45 50 84- ST SUP 76 .NNING 25 4

i m

W tQ O

j #

I O 1

1

A

=

APPENDIX D FORM NIS-1, OWNERS DATA REPORT FOR INSERVICE INSPECTION M

D MLA121384WMH01-LT

i FORM NIS-1 OWNERS' DATA REPORT FOR INSERVICE INSPECTIONS (As Required by the Provisions of the ASME Code Rules) 1.) Owner NORTHERN STATES POWER COMPANY

, Address 414 NICOLLET MALL, MINNEAPOLIS, MN 55401 f

2.) Piant PRAIRIE ISLAND NUCLEAR GENERATING PLANT Address WELSH, MN 3.) Plant Unit 1 4.) Owner (Cartificate of Authorization) - - -

~~

5.) Cournercial Service Date 12-16-73 6.) National Board Number for Unit ~

7.) Components Inspected Manu fa cturer Component or Manu facturer or Installer State or National Appurtenance or Installer Serial No. Province No. Board No.

STEAM GENERATOR TUBING STEAM GENERATOR

1. 11 WESTINGHOUSE 1101 MN 6824 STEAM GENERATOR i #12 WESTINGHOUSE 1102 MN 6825 e

o ISI-1019, Rev. O Page 1 of 2

Fcrm 9-0038,Rev.0 (M&SP 5.2)

FORM NIS-1 (back) 8.) Examination Dates Oct. 23 eo Nov.4,1984 3 . ) Inspe.: tion Interva1 0ec. ,1973 to0ec.,1983 <

10.) Abstract of Examinations. Include a list of examinations and a statement concerning status of work required for current interval.

EXAMINED VARIOUS TUBES IN EACH GENERATOR. EXAMINATIONS FOCUSEDMI TURING

, ADJACENT TO LEAKERS AND IN HfSTORICALLY PREVALENT DEGPAgrn ADFAt.

11.) Abstract of Conditions Noted.

MINIMAL nVER-ALL DEGRADATION DETECTED WITH EXCEPTInNS BEIf'G TU9E3 WHICH EXHIBITED LEAKS VISUALLY.

12.) Abstract of Corrective Measures Recommended and Taken.

ALL DEFECTI5di TUBING WAS REMOVED FROM SERVICE VIA MECHAMICAL PLUGGIMG OF THE TUBE ENDS.

We certify that the statements made in this report are correct and the examinations and corrective measures taken conform to the rules of the ASME Code, Se ci n Date f [9 /

19 ff Signed NORTHERN STATES POWEgy/ 14ot/

l d

Owner Certificatt. of Authorization No. (if applicable)

Expiration Date i

d CERTIFICATE OF UISERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and/or the Staca or Province of,w.dMW 7 4 and employed by#x#rfogy .4n Ac2MDZ o f N44Ws4,o e.*H - c have inspected the com-ponents described in this Owner's Data Report during t?.e period '~o-M- *f F to // 51'9, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners' Data Report in accordance with the requirements of the ASME Code,Section XI.

, By signing this certificate neither the Inspector nor his employer makes any warrancy.

expressed or implied, concerning the examinations and corrective ressures described in this Cwners' Data Report. Furthemore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or loss of any kind arising from or connected with this inspection.

Date _M 9 19 N W W /f .a . Commissions H A P f e V MA ffs~. ~r i/

Insoectorh SienatfFre National Board. State. Province & No.

Page 2 of 2

I t

ATTACHMENT l NRC COMMITTMEf4T REFERENCE A

I MLA121384WMH01-LT

e \o UMTED states Attachment I NUCLEAR REIULATORY COMMISSION Pace 1 of 1

t. was.eweetod. o. c.2 eses

• t

• ese*

k6&

Docket No. 50-282 Mr. D. M. Musolf I

, Nuclear Support Services Department Northern States Power Company 414 Nicollet Mall

, Midland Square - 4th Floor Minneapolis. Minnesota 55401 Deer Mr. Musolf:

We have completed our review of your reevaluation of the eddy current test results transmitted by letter dated June 18, 1984. The eddy current test results are from the December 1983 steam generator tube inspection data of the Prairie Island Generating Plant Unit No.1. This reevaluation was promp-tad by a small primary to secondary leak (approximately 0.015 gpm) detected in February 1984.

Based on our review of your submittal we conclude that, since the identified defects are located within the tubesheet of .the steam generator, they do not at this time constitute an undue hazard to pubite health and safety. On this basis, the Profrie Island Nuclear Generating Plant Unit No.1 can continue to operate provided that the primary to secondary leakage does not exceed 0.3 gpm.

Based on your commitment. if the 0.3 gpa leak rate is exceeded, the unit must be shut down and the defective tubes repaired. In addition, you are requested to infom us of your plans for corrective action if leak rate exceeds 0.15 gpm.

[ Since your reevaluation has uncovered three defective tubes, an inconsistency exists with the technical specification. TS 4.12.D.2. In onier to correct this matter, you are requested to submit a technical specification change request by July 9. 1984 so that a one-time amendment to TS 4.12.D.2 would l pemit continued operation with the three defected tubes in service untti the i and of the current cycle (December 1984).

Our Safety Evaluation is enclosed.

Sincerely.

.,/'_S ( .,*,

4 James R. Miller. Chief Operating Reactors Branch #3 Division of Licensing l o

Enclosure:

As stated cc: See next page 1

TOO T TO *0N G2 9i r8/90 40 l l

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