ML20028E812

LER 83-005/99L-0:on 830107,during Refueling Outage,Helium & Eddy Current Testing Identified Three Degraded Tubes in Steam Generator 2 & Three Degraded Tubes in Steam Generator 3.Tubes Plugged

ML20028E812
Person / Time
Site:	Cook
Issue date:	01/21/1983
From:	Beilman T INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML20028E789	List: ML20028E788 ML20028E801 ML20028E812
References
LER-83-005-99L, LER-83-5-99L, NUDOCS 8301280213
Download: ML20028E812 (3)

Text

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NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION 17 77s i UCENSEE EVENT REPORT - l i

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EVENT DESCRIPTION AND PRO 8ABLE CONSEQUENCES h Q lDURING A UNIT'TWO REFUELING OUTAGE WHICH COMMENCED ON NOVEMBER 21. l' O 3 l1982, HELIUM AND EDDY CURRENT TESTING IDENTIFIED THREE TUBES IN STBAM i

[ TIT) l GENERATOR NO. 2 AND THREE TUBES IN STEAM GENERATOR NO. 3 WHICH EXHIBITEDI

[ TIT] l INDICATIONS ~ OF DEGRADATION AND/OR THROUGH WALL DEFECTS THAT EXCEEDED ~l lO ls l l THE ALLOWABLE CRITERIA AS DEFINED BY 7HE PLANT TECHNICAL SPECIFICATIONS. l l0l7ll l l 10181 l l E CODE 5 BC E COMPONENT CODE S SC DE SU E O 9 lW l El@ J@ l Cl@ l Hj TI . El X l Cl H l@ W@ [ zj @ -

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43 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h li l o l l THE SIX TUBES WERE PLUGGED DUE TO THE HELIUM AND EDDY CURRENT TEST l t i l INDICATIONS . REFER TO THE ATTACHED SUPPLEMENT FOR ADDITIONAT, nPTATTA_ l i 2 l l a i l i 4 l l 7 8 9 80 STA S  % POWER OTHERSTATUS IS O Y DISCOVERY DESCRIPTION h

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SUPPLEMENT TO LER IK). 83-005/99L-0 The purpose of this supplement is to inform you of actions taken by Indiana and Michigan Electric Company in the Steam -

Generators during this refueling outage which commenced November 21, 1982, for the Unit No. 2 reactor.

Eddy Current Testing in the Steam Generators was not re-

, quired during this outage by ASME Code Section XI, 1974 Edition Summer, 1975 Addenda, Regulatory Guide 1.83 or the Unit No. 2 Technical Specifications; as we are presently in the forty-month inspection interval. However, Plant Manage-ment and American Electric Power Service Corporation Management developed a testing and tube plugging program to be performed in Steam Generator Nos. 2 and 3. The following i

summarizes the techniques, findings and remedial measures i taken:

1. Prior to the outage, Steam Generator No. 2 had exhi-bited a leak rate of .264 gallons per minute maximum which is below the Technical Specification limit of

.347 gallons per minute and, as such, did not meet the criteria w:.ich would warrant the performance of an inservice inspection.

A preplanned program to locate the leak included first using a Helium Sniffing technique followed by a Multi-frequency Eddy Current Testing technique programmed to probe all Row 1 and 2 tubes. The Helium Sniffing technique located one Jeaking tube uniquely designated

, Row 1 Column 14. Eddy Current Testing did not confirm the leakage found during Helium Testing but identified instead indications in 2 other tubes designated Row 1 Column 26 (80% wall penettation), and Row 1 Column 47 (100% through-wall defect).

Both indications were found at the tangent point on the hot leg side. Since the Eddy Current Testing did not canfirm the leaks found by Helium Testing, Plant Management elected to perform the Helium Test a second time. The second Helium Test confirmed the results of the first Helium Test.

l Based on Helium Testing and Eddy Current Testing results, tubes designated Row 1 Column 14, Row 1 Column 26, and

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l Row 1 Column 47, were plugged in addition to the planned i plugging of the tubes adjacent to the tube lane block-i ing devices uniquely designated as Row 1 Column 1, Row 4

1 Column 2, Row 1 Column 3, Row 1 Column 4, Row 1 Column 5, Row 1 Column 90, Row 1 Column 91, Row 1 Column 92, Row 1 Column 93, and Row 1 Column 94. The l plugging was accomplished by Westinghouse personnel J

using mechanical plugs.

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' SUPPLEMENT TO LER NO. sa-cos/ gen.o ,

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2. The preplanned examination program for Steam' Generator .l No. 3 included first performing an examination using the Helium Technique followed by an Eddy Current Exami-  !

nation of 935 predetermined tubes using a Multifrequency 1 Technique. No leakage was fotnd using the Helium technique. However, the Eddy Current Examination ..

identified 2 tubes with reportable . indications:in the first selection of tubes. One tube uniquely identified:

Row 44 Column 58 showed 2 indications which measured 41.5% at the No. 3 AVB and 43% at the No. 4 AVB. The other tube identified as Row 37 ' Column 67 showed one indication which measured 38% at the No. 3 AVB.

The results of the examination of the first selection of tubes was evaluated and it was determined that the i

examination program should be expanded in"accordance-with the Donald C. Cook Nuclear Plant Unit No. 2 Technical Specifications. The second selection totaled r 3 62 tu be s . One tube uniquely identified Row 40 Column 36 showed an indication which measured 50% at the~No . 3 AVB.

The results of the examination of the second selection were reviewed and, in accordance with Technical Speci-fications, a decision was made to the expand the program

! a second time. The third selection totaled 1631 tubes.

Reportable indicatons were found in 3 tubes from this selection. Tube uniquely identifi'ed as Row 24 Column

, 61 showed an indication which measured 23% at the No. 3 AVB. Tube designated as Row 24 Column 65 showed 2 indications which measured 23% at t.he No. 2~AVB and 24%

at the No. 1 AVB. Tube designated Row 18 Column 64 showed an indication which measured 22% at the No. 2 AVB.

Three tubes designated Row 44 Column 58; Row 37 Column 67 and Row 40 Column 36 were plugged as a result of Eddy Current Examination.

As a result of a decision to plug Row 1 tubes installed -

adjacent to the tube lane blocking devices, tubes designated Row 1 Column 90, Row 1 Column 91, Row 1 Column 92, Row 1 Column 93, Row 1 Column 94, Row 1 Column 1, Row 1 Column 2, Row 1 Column 3, Row 1 Column 4, and Row 1 Column 5, were plugged.

In addition, 2 tubes designated Row 1 Column 6 and Row 1 Column 7 were plugged as a result of a Westinghouse error.

A total of fifteen (15) tubes were plugged in Steam Generator No. 3 during this refueling outage.

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