ML20155E742

Corrects Error Re Number of Id Iga Indications That Were Reported as Remaining in Svc Following 12R Outage.Revised NIS-1 Owners Data Rept for ISIs & Revised Pages of Rept on 1997 Outage 12R EC Exams of TMI-1 OTSG Tubing, Encl

ML20155E742
Person / Time
Site:	Three Mile Island
Issue date:	10/28/1998
From:	Langenbach J GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20155E747	List: ML20155E742 ML20155E751
References
1920-98-20206, NUDOCS 9811050167
Download: ML20155E742 (3)

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• GPU Nuclear. Inc.

( Route 441 South NUCLEAR Po't Dc' Bon '80 Middletown. PA 17057-0480 rel 717 944 7621 October 28, 1998 l

1920-98-20206 i l

U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 l Gentlemen:

Subject:

Three Mile Island Nuclear Station, Unit 1 (TMI-1)

Docket No. 50-289 Operating License No. DPR-50 GPU Nuclear Cycle 12 Refueling (12R) Outage Once Through Steam Generator (OTSG) Tube Inspection Report with ASME NIS Data Reports for Inservice Inspections (ISI)- Revision 1 GPU Nuclear submitted the Cycle 12 Refueling (12R) Outage Once Through Steam Generator (OTSG) Tube Inspection Report with ASME NIS Data Reports for Inservice Inspections (ISI) on January 12,1998. Recently an error has been discovered in the number ofinside diameter (ID) inter-granular attack (IGA) indications that were reported as remaining in service following the 12R Outage. Since the original submittal did not account for the tubes that were removed from service by plugging, the number of volumetric ID IGA indications remaining in service is fewer than that reported. The purpose of this letter is to correct the error and submit a revised NIS-1 Owners' Data p/

Report for Inservice Inspections (attached) along with the revised pages of the " Report on the 1997 '1 Outage 12R Eddy Current Examinations of the TMI-l OTSG Tubing."

Sincerely, dj 9811050167 981028

• I PDR ADOCK 05000289 1 James W. La ge'nbach G PDR Vice President and Director, TMI MRK ,

Attachments cc: Administrator, NRC Region I

. TMl Senior NRC Resident inspector TMI-l Senior NRC Project Manager PA DOLI Hartford Steam Boiler I&l Co.

File No. 97087

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FORM NIS 1 OWNERS' DATA REPORT FOR INSERVICE INSPECTIONS As required by the Provisioas of the ASME Code Rules

1. Owner Metropolitan Edison Co. 2800 Pottsville Pike,Readin9, Pennsylvania (Name and Address of Owner)

2. Plant Three Mile Island Nuclear Generating Station Route 441 South, Middletown, Pa.

(Name and Address of Plant)

3. Plant Unit Unit 1 4. Owner Certificate of Authorization (if required) N/A

5. Commercial Service Date H9/H2/74 6. Nationai Board Number for Unit Reactor vessel n_1og

7. Components inspected l

Man'ifar rer  !

Component or Manufacturer or der State or National  !

Appurtenance or Installer Serial no. Province No. Board o.

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N/A

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Note: Supplemental sheets in form of lists, sketches, or drawings may be used provided (1) size is 8% in. x 11 in.,  ;

(2) information in items 1 through 6 on this data report is included on each sheet, and (3) each sheet is numbered ,

and the number of sheets is recorded at the top of this form.

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This form (E00029) may be obtained from the Order Dept., ASME,345 E. 47th St., New York, N.Y. 10017 j

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FORM NIS 1 (back) 8.~ Examination Dates 10/12/95 to 10/31/91 9. Inspection Interval from 1991 to 9nni 10, Abstract of Examinations. Include a list of examinations and a statement concerning status of work required for current interval. This NIS-1 submittal is a correction for NIS-1 submittal approved January 12, 1998 See attached Enclosure 1 for correction.

11. Abstract of Conditions Noted See attached Enclosure, Revision 1, correction.

12. Abstract of Corrective Measures Recommended and Taken Submitted in NIS-1 approved January 12, 1998.

a We certify that the statements made in this report are correct and the examinations and corrective mea-sures taken conform to the rules of the ASME Code,Section XI.

Date .Cc TStad (( 19 % Signed Mc.A NBC/lBi SE9LBy _'

Owner f~ (/

Certificate of Authorization No. (if applicable) _hA Expiration Date __g[A

CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and/or the State or Province of Pa. and employed by it. S . B . I . &I . Company of HnG [ond, Ct. have inspected the components described in this Owners' Data Report during the period 10/12/95 to 10/31/97 . and state that to the best of my knowledge and belief, the Ownce has perfonned 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' Data Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personalinjury or property damage

< or a loss of any kind arising from or connected with this inspection.

Date _ 4 7' S 19 78

_ ._. Commissions NR 54 78 fI1 (4) Da. 1887 Inspector's Signatur[ National Board, State. Province and No, 1

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. i Attaciunent i REVISION I PAGE2 TABLE. OF CONTENTS

. , PAGE NO.

]

1. , INTRODUCTION 5 l

. II. METilORS 6 A DATA ACOUISITION 6

1. Tube Bobbin Coil Examinations 7

2. Sleeve Bobbin Coil Examinations 7

3. Motorized Rotating Pancake Coil (MRPC) Tube Examinations 8

4. Plus Point Examinations of Sleeves 8 B. D_ATA ANALYSIS PROCESS 8

.l. Data Analyst Oualitications 8

2. Data Analysis Seouence 8

3. Data Analysis Software 9

4. Recording ofIndications 9

5. . Data Management to C. DISPOSITION OF RESULTS 11

1. Inside Diameter IGA 11

2. Kinetic Expansion Region 11

3. Q1her Indications 15 D. IN SITU PRESSURE TESTING 15

1. Pressure Test Process 19

2. Tube Selection 16 E. TUBE REMOVAL 17

1. , Selection of Tubes 17

2. Pre-removal NDE 17

3. Removal Methods 18 F. RECORDS 18

' Ill. OUTAGE 12R EXAMINATION CATEGORIES AND RESULTS 21 A. SCOPE SELECTION 21 B. TUBE EXAMINATION RESULTS 30

1. Tube Examinations funexpanded region) 30

2. Kinetic Expansion Examjnations 44

3. Lanc/ Wedge Examinations 48

4. Rerolled Tube Examinations 48

5. Sleeve Examina.tiqns 48 C. IN-SITU PRESSURE TESTING 48 D. TUBE REMOVAL $0

1. 'ECT Results 50

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