Text

Inservice Insp,Examination Summary,791003-16,Insp Period 2, Steam Generator Tube Eddy Current Exam
	ML19260B228
Person / Time
Site:	Prairie Island
Issue date:	11/07/1979
From:	Dahlman L, Hansen D; NORTHERN STATES POWER CO.
To:	;
Shared Package
ML19260B225	List: ML19260B224; ML19260B228;
References
	NUDOCS 7912070440
	Download: ML19260B228 (41)
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.

PRAIRIEISLAND NUCLEAR GENERATING PLANT m

Redwing, Minnesota 3

UNITS 1 AND 2 I

o MHNEAPOLIS2 ST. PAUL 5

is' s e"a$wt INSERVICE INSPECTION-EXAMINATION SUWARY for.the PRAIRIE ISLAND NUCLEAR GENERATING PLANT UNIT I CCTOBER 3 TO OCTOBER 16, 1979 INSPECTION PERIOD 2 STEAM GEFERATOR TUBE-EDDY CURRENT EXAMINATION REPORT DATE:

NORTHERN STATES POWER COMPANY C0:@iERCIAL SERVICE Date: 12-16-73 November 7, 1979 MINNE APOLIS. MINNESOTA 1514 180 Y

7912070

NORTHERN STATES POWER COMPANY INSFrJ.' ICE INSPECTION-EXAMINATION

SUMMARY

FOR THE PRAIRIE ISLAND NUCLEAR GENERATING PLANT-UNIT I OCTOBER 3 to OCTOBER 16, 1979 Inspection Period 2 STEAM GENERATOR TUBE-EDDY CURRENT EXAMINATION COMMERCIAL SERVICE Prepared by:

D. B.

Hansen, Asst DATE:

12-16-73 M&SP Engineer Lanny Dahlman, M&SP Specialist Reviewed by:

\\.

REPORT DATE:

11-7-79 p, y e krump[/s, Supt Material and Special Processec Approved by:

A Ra f. Anderson, Gen.

Superintendent, Prod. Plant Maintenance 1514 181

NORTHERN STATES POWER COMPANY PRAIRIE ISLAND NUCLEAR GENERATING PLANT-UNIT 1

-INDEX-1.0 Introduction 2.0 Discussion of Examination Plan 3.0 Corrective Action i

4.0 Examination Procedures 5.0 Materials and Equipment 6.0 Personnel 7.0 Summary of Results Appendix A - Steam Generator No. 11 Eddy Current Examination Results and Tube Sheet Maps Appendix B - Steam Generator No. 12 Eddy Current Examination Results and Tube Sheet Maps Appendix C - Steam Generator No. 11 & 12 Accumulative Eddy Current Examination Tube Sheet Maps Appendix D -

Table I - Personnel Listing Table II-Procedure Listing Table III-Equipment and Materials Appendix E - Form NIS-1, Owners' Data Report for Inservice Inspection Appendix F - Spring Location and Tube Wear Figures 9

1514 182

INSERVICE INSPECTION-EXAMINATION

SUMMARY

FOR THE PRAIRIE ISLAND NUCLEAR GENERATING PLANT-UNIT I October 3 to October 16, 1979 1.0 Introduction This report is a summary of the Steam Generator Tube Eddy Current d

examination performed at Prairie Island Unit I.

The examinations were performed during the period of October 3 througd 0ctober

.16, 1979, af ter a tube break occured on October 2,1979. Prairie Island Unit I began commercial operation on December 16, 1973.

An Eddy Current examination program of the Steam Generator Tubes was conducted with the following objectives:

(1) To identify the ruptured tube, (2) To obtain information on the possible cause of the tube rupture, (3) To detect any further tube degradation in the steam generator, and (4) To determine the general condition of the steam generator tubing.

This was the sixth inservice inspection conducted on steam gen-erator tubes since the date of commercial operation. Eddy current examinations were performed on both steam generators during 1974, 75, 76, and 77; and on steam generator #12 during 1978. Similar procedures vnd equipment have been used for all of the inservice inspections.

The steam generator tube sheet maps, examination method and results are summarized in the tables of the attached appendices as follows:

Appendix A - Steam Generator No. 11 Eddy Current examination results and tube sheet maps Appendix B - Steam Generator No. 12 Eddy Current examination results and tube sheet maps Appendix C - Steam Generator No. 11 & 12 Accumulative Eddy Current examination tube sheet maps.

2.0 Discussion of Examination Plan The evaluation of the break and identification of the exact failed tube was accomplished by draining water frc a the secondary side of the steam generator into the RCS through the opening of the leaking tube. Once the water on the secondary side stopped draining, the break clevation was determined. Then by slowly adding water to the secondary side and visually inspecting the tube sheet from the primary 1514 183 Page 1 of 5

B side through the manways, t'2 specific tube was identified.

Since the leaking tube (Row 4, Column 1, Inlet side) was located in the outer periphery of the tube bundle and the break was just above the tube sheet within the flow lane, foreign object damage was suspected. Therefore, the eddy current inspection was con-centrated in the outer periphery tubes.

The inspection program was conducted in accordance with Technical Specifications, Section 4.12.

The results of the eddy current examinations revealed that the Row 3, Column 1 tuba (adjacent to the failed tube) had indication of a 65% reduction in wall thickness.

The Row 2, Column 1 tube (next tube) hoc a possible indication of (20% reduction in vall thickness. All of these indications were at approximately the same elevation.

With the aid of mirrors and fiber optics, a visual examination of the three degraded tubes verified the eddy current results and revealed that the break resembled a classical overpressure burst (running approximately 1h" in the longitudinal direction of the tube with an opening width of approximately h").

The other tubes (Row 3, Column 1 and Row 2, Column 1) showed signs of wear. All wear marks verm on the outer peripheral side of the tubes. These patterns were documented by photographs and are depicted in Appendix F, Figure 1.

During this time, a coil spring, later measured to be 8.5" long, 1.25" diameter, and 3/32 gauge was found to be lying on the tube sheet adjacent to the defective tubes. One end of the spring was lodged under the tube land blocking device and the other end was free to move.

Figure 2 in Appendix F is an overhead view showing the location of the spring, tube lane blocking device, and the peripheral tubes. Figure 3 is a side view, and figure 4 is a front view. A definite wear pattern on the tube sheet indicated that the spring had moved during operation. Later, a second spring, identical to the first, was found on the cold leg side. It was located just opposite the first spring in a similar condition with one end lodged under the tube lane blocking device and the other end extending out onto the tube sheet.

In addition, part of an aviation hose clamp was found next to this spring on the cold leg side. A close visual examination of the spring on the cold leg side, the tubes and the tube sheet surface revealed no signs of spring movement, tube damage or wear. This was confirmed by eddy current examination of all eight tubes in Column 1 in close proximity to the second spring.

Once these objects were removed from the steam generator it was ap-parent that the spring and piece of hose clamp from the cold leg side were encrusted with oxides indicating no active movement while the coils of the spring from the hot leg side had definite signs of wear.

A complete visual examination of the outer peripheral area of the tube bundles and the flow lanes for both steam generators revealed no other signs of foreign objects.

In addition, the eddy current examinations conducted for both steam generators revealed no other tubes with wear or degradation.

Page 2 of 5

~

1514 184

3.0 Corrective Action The springs ha'e been shipped to Westinghouse for further examination.

The springs and clamp appear to have been part of sludge lancing equipment used in one of the previous outages. It appears that this spring was dropped into the steam generator prior to installation of the tube lane blocking device. Investigations in this area are continuing.

Three ccurses of corrective action were identified based on the following facts:

(1) The pattern of tube wear (2) The location of tube wear relative to the spring location (3) The wear pattern of the spring on the tube sheet (4) The signs of wear on the spring wire (5) No other tubes that were inspected other than the three previously discussed had any signs of wear or tube degradation (6) No other foreign objects were found.

It has been concluded that the tube break was the result of reduction of wall thickness by the wearing action of the spring against the tube.

The three courses of corrective actions identified were:

(a) plug the two defective tubes and several adjacent tubes, (b) remove a section of the defective Row 4 tube and plug the two defective tubes, or (c) stabilize the defective Row 4 tube from the primary side and plug the two defective tubes. Discussions among NSP, Westinghouse, and NRC staff revealed that option (a) should be selected for several.

reasons-(1) in accordance with ALARA, the occupational exposure would be

least, (2) uncertainties in the design concept of tube stabilization,

and, (3) minimize effects of possible instability of the defective Row 4 tube.

In addition to the failed tube, and the tube with 65% wall reductica, the remaining four adjacent tubes to the failed tube were plugged.

This action was taken to eliminate the remote possibility of the f ailed tube breaking further and damaging the adjacent tubes. A secondary side pressure test was conducted to assure leak tightness of the plugs.

4.0 Examination Procedures The eddy current examination, equipment and procedures that were used for this inspection were virtually equivalent, with the excep-tion of the small radius U-bend examination, to those procedures used for previous examinations. All examinations were performed using an internal dual coil differential probe and Za*.

Corp-oration's eddy current test system capable of display 1r.g both amplitude and phase of each response from anomalies in the tubing.

1514 185 Page 3 of 5

The examination data was recorded on both a conventional two channel strip chart and magnetic tape recorder. The strip charts were used for quick evaluation of each tests and the magnetic tape recordings were replayed into a tester for detailed analysis of indications.

The examination for defects were performed at 400 KHz and 100 KHz (small radius U-bend). The small radius U-bend exam-ination utilized the same equipment with the exception of a special designed eddy current probe. The probe design resembles a string of beads that permits passage through the small radius U-bends. The U-bend examination uses two probes, one for the inspection and an identical probe fixed in the absolute test standard for comparison.

The procedures used for the eddy current examinations are listed in Table II of Appendix D.

5.0 Equipment and Materials All equipment and expendable materials used in the examinations are listed by either serin 1 number or type along with their respective calibration date or batch number in Table III of Appendix D.

6.0 rersonnel Northern States Power Company contracted Westinghouse, with technical eddy current examination support from Zetec Cor-poration, to perform and evaluste the eddy current examinations.

Hartford Steam Boiler Insurance and Inspection Company, represent-ing ANI, provided the Authorized Inspection.

All personnel involved in the performance or evaluation of exam-inations are listed along with their title, organization and ASNT level of certification in Table I of Appendix E.

Certifications for examination personnel are maintained on file by Northern States Power Company.

7.0 Summary of Results The two springs found in Steam Generator No. 11 have been shippad to Westinghouse for further examination.

The complete visual examination of the outer peripheral area of the tube bundles and the flow lanes for both steam generators revealed no additional foreign objects or other abnonnalities.

The evaluation of the eddy current examination results disclosed no other tubes with wear or with degradation. On Steam Generator No. 11, e total of 688 tubes were inspected for defects, and a total of 630 tubes were inspected on Steam Generator No. 12.

Page 4 of 5

)hj4

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The examination type and extent were perforr.ed as follows:

Exam Exan Exam Tube Amount Frequency Extent percentage Steam Generator No. 11 Inlet 105 100KHz Tight Radius U-bends 3.1 %

227 400KHz Around U-Bends 6.7 %

348 400FFz Past 7th Support 10.27%

No. 11 Outlet 8

400.Hz Past 1st Support

.2 %

Steam Generator No. 12 Inlet 90 100KHz Tight Radius U-Bends 2.6 %

304 400KHz Around U-Bends 8.97%

236 400KHz Past 7th Support 6.96%

A detailed listing of all indications and a comparison to previous examinations is included in Appendix A and B, for Steam Generator No. 11 and 12 respectively. A 'otal of 6 tubes were plugged during this outage; the failed tube, the tube with a 65% wall reduction, and the four surrounding tubes.

,5 4

6/

Page 5 of 5

-6 9

APPENDIX A STEAM GENERATOR NO.11 EDDY CURRENT EXAMINATION RESULTS AND TUBE SHEET MAPS O

1514 188

EDDY CURRENT EXAMINATION RESULTS PRAIRIE ISLAND - UNIT I APPENDIX A STEAM GENERATOR NO.

11 PAGE _L OF_jt INLET (HOT LEG)

EXAMINATION FREQUENCY 400KHz DATE Oc t. 1979 R0W COLUMN INDICATION LOCATION PRIOR EXAMINATION INDICATIONS 4

1 DENT

1 T.S.P.

NA 4

1 100%

43h"above T.S.

NA (2 "-5" above T.S.)

3 1

65%

5" above T.S.

NA (approx 1" in length) 2 1

Possible (20%

5" above T.S.

NA 5

3 DENT

7 T.S.P. (small)

NA 7

4 DENT

7 T.S.P.(small)

NA 8

4 DENT

7 T.S.P. (small)

NA 9

4 DENT

7 T.S.P. (small)

NA 9

5 DENT

7 T.S.P. (small)

NA 8

5 DENT

7 T.S.P. (small)

NA 7

5 DENT

7 T.S.P. (small)

NA 11 4

DENT

7 T.S.P. (H.L.)

NA 12 2

DENT

7 T.S.P. (H.L.)

NA 13 3

DENT

7 T.S.P. (H.L.)

NA 15 3

DENT

7 T.S.P.(H.L.)

NA 15 4

DENT

7 T.S.P.(H.L.)

NA 42 30 DENT

6 T.S.P.(H.L.)

NA 43 30 DENT

6 T.S.P.(H.L.)

NA 43 31 DENT

6 T.S.P. (H.L.)

Manufact'uring Dent 0 #6 support 1514 i89

EDDY CURRENT EXAMINATION RESULTS PRAIRIE ISLAND - UNIT I APPENDIX A STEAM GENERATOR NO.

11 PAGE 2 0F 6'

INLET (HOT LEG)

EXAMINATION FREQUENCY 400KHz DATE Oct. 1979 RON COLUMN INDICATION LOCATION PRIOR EXAMINATION INDICATIONS 43 32 DENT

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NA 44 33 DENT

6 T.S'.P.(H.L.)

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NA 44 36 DENT

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NA

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NA

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40 DENT

66#7 T.S.P.(C.L.)

NA 45 41 DENT

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NA 45 55 DENT

7 T.S.P.(C.L.)

NA 45 56 DENT

7 T.S.P.(C.L.)

NA 45 57 DENT

7 T.S.P.(C.L.)

NA 44 58 DENT

7 T.S.P.(C.L.)

NA 44 59 DENT

7 T.S.P. (C.L.)

NA 42 59 DENT

7 T.S.P.(C.L.)

NA 1514 190

EDDY CURRENT EXAMINATION RESULTS PRAIRIE ISLAND - UNIT I APPENDIX A STEAM GENERATOR NO. _JJ_

PAGE 3 0F 6 INLET (HOT LEG)

EXAMINATION FREQUENCY 400KHz DATE Oct. 1979 R0W COLUMN INDICATION LOCf.

~~d PRIOR EXAMINATION INDICATIONS 44 62 DENT

7 T.S.P.(C.L.)

NA 43 62 DENT

7 T.S.P.(C.L.)

NA 43 64 DENT

7 T.S,.P.(C.L.)

NA 43 65 DENT

7 T.S.P.(C.L.)

NA 42 64 DENT

7 T.S.P.(C.L.)

NA 42 65 DENT

7 T.S.P.(C.L.)

NA 42 67 DENT

6 T.S.P.(C.L.)

NA 41 67 DENT

7 T.S.P.(C.L.)

NA 41 68 DENT

7 T.S.P.(C.L.)

NA 15 92 DENT

7 T.S.P.(C.L.)

NA 25 48 Distorted tube sheet

=

NA 22 48 Distorted tube sheet NA 21 48 Distorted tube sheet

=

NA 21 47 Distorted tube sheet

--==

NA 20 47 Distorted tube sheet NA 20 48 Distorted tube sheet NA 19 48 Distorted tube sheet NA 19 47 Distorted tube sheet P.V. 36"above T.S.

18 47 Distorted tube sheet NA 18 48 Distorted tube sheet NONE 17 48 Distorted tube sheet NA 17 47 Distorted tube sheet NA l514 191

EDDY CURRENT EXAMINATION RESULTS PRAIRIE ISLAND - UNIT I APPENDIX A STEAM GENERATOR NO.

11 P AGE 4 0F 6 INLET (HOT LEG)

EXAMIFATION FREQUENCY 400KHz DATE Oct.,1979 ROW COLUMN INDICATICN LOCATION PRIOR EXAMINATION INDICATIONS 16 47 Distorted tube sheet NA 16 48 Distorted tube sheet NA 15 48 Distorted tube sheet None 15 47 Distorted tube sheet NA 15 46 Distorted tube sheet NA 14 47 Distorted tube sheet NA 14 48 Distorted tube sheet NA 12 48 Distorted tube sheet Manufacturing Dent U-Bend, Centerline 10 40 Distorted tube sheet

==

NA 15 34 Distorted tube sheet NA 10 34 Distorted tube sheet NA 15 28 Distorted tube sheet

=-

NA 20 28 Distorted tube sheet NA 25 28 Distorted tube sheet NA 1

10 Distorted tube sheet FONE

~

l 19 Dent

7 T.S.P. (H.L.)

NA 1

20 Dent

7 T.S.?. (H.L.)

NA 1

60 Distorted tube sheet NA 1

69 Distorted tube sheet NA 1

70 Distorted tube sheet NA

EDDY CURRENT EXAMINATION RESULTS PRAIRIE ISLAND - UNIT I APPENDIX A STEAM GENERATOR NO.

11 PAGE 5 0F 6 INLET (HOT LEG)

EXAMINATION FREQUENCY 400KHz DATE Oct. 1979 ROW COLUMN INDICATION LOCATION PRIOR EXAMINATION INDICATIONS 1

71 Distorted tube sheet NA 2

72 Distorted tube sheet

- - - = =

NA 1

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==-

NA 2

73 Distorted tube sheet

=

NA 1

82 Distorted tube sheet NA 1

84 Distorted tube sheet NA 1

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7 T.S.P. (C.L.)

NA 47 61 Dent

7 T.S.P. (C.L. )

NA 43 61 Dent

7 T.S.P.(C.L.)

NA 43 60 Dent

7 T.S.P.(C.L.)

NA 42 60 Dent

7 T.S.P.(C.L.)

NA 44 37 Dent

6 T.S.P.(H.L.)

NA 42 36 Dent

6 T.S.P.(H.L.)

NA 43 36 Dent

6 T.S.P. (II.L. )

NA 43 35 Dent

6 T.S.P. (ll.L. )

NA 42 35 Dent

6 T.S.P. (II.L. )

NA 42 33 Dent

6 T.S.P.(H.L.)

NA 3'

19 Dent

7 T.S.P.(C.L.)

NA 12 4

Dent

7 T.S.P.(H.L.)

NA 3

1 65%

5" above T.S.

NA 1514 193

EDDY CURRENT EXAMINATION RESULTS A

PRAIRIE ISLAND - UNIT I APPENDIX STEAM GENERATOR NO.

11 PAGE J OF J OUTLET (COLD LEG)

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STEAM GENERATOR NO. 11 " INLET" 100 Kriz Exam:

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STEAM GENERATOR NO. 11 OUTLET" 400 KHz Exam: @ Tubes Inspected to First Support

1 APPENDIX B STEAM GENERATOR NO. 12 EDDY CURRENT EXAMINATION RESULTS AND TUBE SiiEET MAPS 1514 198

EDDY CURRENT EXAMINATION RESULTS PRAIRIE ISLAND - UNIT I APPENDIX B STEAM GENERATOR NO.

12 PAGE 1 0F 3 INLET (HOT LEG)

EXAMINATION FREQUENCY 400KHz DATE nce,107o R0W COLUMN INDICATION LOCATION PRIOR EXAMINATION INDICATIONS

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Permeability variatico 35"above #6 NA T.S.P.

45 57 Dent 7th T.S.P.(C.L.)

NA 45 58 Dent 7th T.S.P.(C.L.)

NA 44 58 Dent 7th T.S.P.(C.L.)

NA 43 59 Dent 7th T.S.P.(C.L.)

NA 44 59 Dent 7th T.S.P. (C.L.)

NA 45 59 Dent 7th T.S.P.(C.L.)

NA 44 60 Dent 7th T.S.P._(C.L.)

NONE 43 60 Dent 7th T.S.P. (C.L.)

NA 44 61 Dent 7th T.S.P.(C.L.)

NA 43 62 cent 7th T.S.P.(C.L.)

NA 42 62 Dent 7th T.S.P.(C.L.)

NA 39' 71 Dent

' tween #3&#4 Anti-NA

/ibration Bars 19 90 Permeability variation 5"above #2T.S.P.

NA 10 91 Permeaoility variation 29"above#1T.S.P.

NA 1

15 Permeability variation 3etween#3&#4 T.S.P.

NA 1

72 Dent 3"above tube sheet Dent-3"above tube sheet 2

75 Permeability variation 18" above #4 T.S.P NA 2

84 Permeability variation 34"above#4 T.S.P.

NA 2

85 Permeability variation 32"above#3 T.S.P.

NA 1514 199

EDDY CURRENT EXAMINATION RESULTS PRAIRIE ISLAND - UNIT I APPENDIX B STEAM GENERATOR NO.

12 PAGE l 0F l INLET (HOT LEG)

EXAMINATION FREQUENCY 400KHz DATE Oct.,1979 ROW COLUMN INDICATION LOCATION PRIOR EXAMINATION INDICATIONS 16 51 Distorted tube sheet

--==

NA 16 45 Distorted tube sheet NA 22 39 Distorted tube sheet NA 11 27 Distorted tube sheet NA e

1G1 L

EDDY CURRENT EXAMINATION RESULTS PRAIRIE ISLAND - UNIT I APPENDIX B STEAM GENERATOR NO.

12 PAGE 3 0F 3 I.4LET (HOT LEG)

EXAMINATION FREQUENCY 100Klfz DATE Oct.,1979 ROW COLUMN INDICATION LOCATION PRIOR EXAMINATION INDICATIONS No.letectable defects on all tubes examined 4

"h=

1514 201

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NOZZLE

=

+MANWAY STEM GENERATOR NO.12 " INLET" 100 KHZ Exam:

A Tubes Inspected Absolute Method Tight Radius U-Bend

APPENDIX C STEAM GENFRATOR ::0. I1 6 12 ACCUMULATIVE EDDY CURRENT EXAMINATION TUBE SilEET MAPS 1514 ^J4

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+M ANWAY rr tr2 2 2 ad *ciar caaattas et=== c=ie 2 NOZ ZLE--*

STEAM CENERATOR NO.

11 " OUTLET" 400 KHz Examinations

$ Tubes Inspected Through U-Bend N

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O

+MMWM ' TEAM CENERATOR No.12 " INLET" NMRE*

' '"' ""*2**' '*"**"* "* "" '

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$ Tubes Inspected Through U-Bend 3:; of g Tubes Inspected to Top (7th) Support

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N

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NOZZLE

oU O

400 KHz Examination:

g Tubes Inspected Through U-Bend Q

M or g Tubes Inspected to Top (7th) Support Q Tubes Inspected to Tirst Support

APPENDTX D PERS0!C4EL LISTING TABLE I TABLE II

- PROCEDURE LISTING TABLE III

- EQUIPMENT AND MATERIAL 1514 209

PRAIRIE ISLAND UNIT I APPENDIX D PERSONNEL LISTING TABLE I PAGE 1 of 1 I

EXAMINER TITLE ORGANIZATION ASNT LEVEL ET R.

Cottrell Technician W(1)

I F. D.

Dawson Technician W

I R. P.

Hazen Technician W

II R. H.

Ingraham Technician W

II E. O.

McKee Evaluator ZETEC(2)

IIA W. E.

Monroe Technician W

I T. A.

Pfarr Technician W

I E.

Westbrook Supervisor W

IIR D.B.

Hansen Asst M & SP NSP Engineer P. J.

Krumpos Superintendent NSP M & SP C.

Linstrom ANII Hartford Steam Boiler Inspection and Insurance Co.

FOOTNOTES (1) ORGANIZATION: Westinghouse Electric Corporation Nuclear Services Division P.O.

Box 2728 Pittsburgh, Pa.

15230 (2) ORGANIZATION: ZETEC P.O.

Box 140 Issaquah, Washington E;027 1:)l4 210

PRAIRIE ISLAND UNIT I APPENDIX D PROCEDURE LISTING TABLE II PAGE 1 of 1 OCEW RE U M MT SO Gl GE DA E MRS 2.4.2 GEN-!8 NONE Eddy Current Inspection of Steam 10-5-79 NONE Revision 2 Generator Tubing-Preservice and Inservice Technical Supplement NONE Steam Generator Tubing Inspection 10-5-79 NONE No. I to MRS 2.4.2 for Tube Wall Degradation-GEN-18 Detection and Quantification Revision 5 Technical Supplement NONE Steam Generator Tubing Inspection 10-5-79 NONE No. 4 to MRS 2.4.2 for Low Level Tube Wall Degrad-GEN-18 ation Revision 0 Technical Supplement 1

Steam Generator Tubing Inspection 10-5-79 Field Change No. I added No. 5 to MRS 2.4.2 for Tube Wall Degradation to incorporate " absolute GEN-18 Tight Radius U-Bends test" method for tight Revision 0 radius U-Bends.

~~'

Ln MRS 2.4.2 GEN-19 NONE Installation and Removal of Eddy 10-5-79 NONE Revision 0 Current Positic ing Devices pg)

~

N I

PRAIRIE ISLAND UNIT I APPENDIX D EQUIPMENT AND MATERIALS TABLE III PAGE 1 of 1 EQUIPMENT OR TYPE OR SERIAL #

CALIBRATION DATE MATERIAL OR BATCH NUMBER REMARKS WESTINGHOUSE FM Tape Racorder 0520 10-3-79 FH Tape Recorder 0273

' 's-3-7 9 Brush MK220 0025 9-14-79 Brush MK220 0156 6-26-79 EM 3300 0517 5-29-79 EM 3300 0157 5-3-79 Storage Scope 0005 5-29-79 Model SIG3 Storage Scope 0010 5-3-79 Model 5103 ZETEC FM Tape Recorder 049 7-12-79 Oscilloscope B065175 8-6-79 Model 5403 Vector Analyzer 006 8-6-79 CALIBRATION STANDARDS I-32-W In-Line Standard Heat No.8791 NX-7735 Absolute Standard lleat No.NX-7785 POWER WEIGHTS 1-100g.

S/N M-97 5-23-79 NISSEN MARKERS White Lot #2, Coded U2All 6-28-77 1514 212

APPENDIX E FORM NIS-1 OWNERS' DATA REPORT FOR INSERVICE INSPECTION 4

1514 213

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, MINNESOTA 2.)

Plant PRAIRIE ISLAND NUCLEAR GENERATING PLANT-UNIT 1 Address WELCH, MINNESOTA 3.)

Plant Unit 1

4.)

Owner (Certifica te of Authoriza tion)--- ---

5.)

Commercial Service Date12-16-73 6.)

National Board Number for Unit-----

7.)

Components Inspected Manu fa cturer Component or Manu fac turer or Installer State or National Appurtenance or Installer Serial No.

Province No.

Board No.

STEAM GENERATOR TUBING S/G NO. 11 WESTINGHOUSE 1101 68-24 INLET TUBE EXAMINATION EXAMINATION EXAMINATION AMOUNT FREQUENCY EXTENT PERCENTAGE 105 100KHz, Absolute Tight Radius 3.1%

U-Bends 227 400KHz Around U-Bends 6.7%

348 400KHz Past 7th Sur, ort 10.27%

OUTLET TUBE AMOUNT 8

400KHz Past 1st 2%

STEAM GENERATOR TUBING e

S/C NO. 12 U"CflNGHOUSE 1102 68-25 INLET TUBF EXAMINATION EXAMINATION EXAMINATION AMOUNT FREQUENCY EXTENT PERCENTAGE 90 100KHz, Absolute Tight Radius U-Bends 2.6%

304 400KHz Around U-Bends 8.97%

236 400KHz Past 7th Suppart 6.96%

Form No. 3-3048-1 Page 1 of 2

FORM NIS-1 (back) 8.)

Examina tion Dates 10-3 to 10-16-79 9.)

Inspection Interval 12-16-73 to 12-16-83 10.) Abstract of Examinations. Include a list of examinations and a statement concerning status of work required for current interval.

This was the sixth inservice inspection conducted on steam generator ttbes since the date of commercial operation. During this outage 688 tubes were inspected for defects on Steam Generator No, 11; and, 630 tubes were inspected for defects on Steam Generator No. 12.

The examinations competed the Eddy Current Examination requirements for Inspection Period 2, in accordance with Prairie Island Technical Specifications, Section T.S. 4.12.

I 11.) Abstract of Conditions Noted.

Two springs and a piece of hose clamp were found in Steam Generator No. 11.

A visual examination revealed one leaking tube (Row 4, Column 1) on the inlet side of Steam Generator No. 11.

Eddy Current Examinations revealed Row 3 Column 1 tube had indication of a 65% reduction in wall thickness, and Row 2 Column 1 tube had a possible indication of 20% reduction. Visual and Eddy Current Examinations revealed no other foreign objects or tubes with wear or 12.) AbstDb'lDkbective Measures Recommended and Taken.

The two springs found in Steam Generator No. 11 have been shipped to Westinghouse for~further examination. A total of 6 tubes were plugged during this outage; the failed tube, the tube with a 65% wall reduction, and the four surrounding tubes.

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,Section XI.

Date //./5 19 79 SignedA$arww/ furs A.wp By gI [Mmw Owner CwsNxy

[

Certificate of Authorization No. (if Applicable)

Expir tion Date CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors jnd/or the State or Province of fdl,u,v e s. yk.and employed by//.,M,,2 J/. fl,.M,. 4 M W. of //,,. M, d Po.o as.

have inspected the com-ponents described in this Owner's Data Peport during the period

/c-5 to /e./ 6 79, 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 warranty, expressed or implied, concerning the examinations and corrective measures described in this Owners' 'ata Report. Fu r the rmo re, 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.

Da t e,

/[- I S' 19 73 E eL Commissions / 8 69,3 7 4/. 800-69 f/

9 Ins'pec tor s Siena ture National Board. State, Province & No.

f Form No. 3-3048-2 Page 2 of 2 1514 215

APPEN;)IX F SPRING LOCATION and TUBE WEAR FIGURES a

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SUMMARY

SUMMARY

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