05000244/LER-1981-009-01, /01T-0:on 810515,fifteen Tubes in Steam Generator B Showed Indications.Caused by Concentration of Caustics in Crevices Leading to Intergranular Attack & Wedge Area Defect in One Indication.Tubes Welded or Mechanically Plugge

/01T-0:on 810515,fifteen Tubes in Steam Generator B Showed Indications.Caused by Concentration of Caustics in Crevices Leading to Intergranular Attack & Wedge Area Defect in One Indication.Tubes Welded or Mechanically Plugged

ML17309A161
Person / Time
Site:	Ginna
Issue date:	05/29/1981
From:	Larizza G ROCHESTER GAS & ELECTRIC CORP.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML17309A162	List: 05000244/LER-1981-009, Forwards LER 81-009/01T-0 05000244/LER-1981-009-01, /01T-0:on 810515,fifteen Tubes in Steam Generator B Showed Indications.Caused by Concentration of Caustics in Crevices Leading to Intergranular Attack & Wedge Area Defect in One Indication.Tubes Welded or Mechanically Plugge
References
CAR-1303, LER-81-009-01T, LER-81-9-1T, NUDOCS 8106030317
Download: ML17309A161 (4)

LER-1981-009, /01T-0:on 810515,fifteen Tubes in Steam Generator B Showed Indications.Caused by Concentration of Caustics in Crevices Leading to Intergranular Attack & Wedge Area Defect in One Indication.Tubes Welded or Mechanically Plugged

Event date:
Report date:
2441981009R01 - NRC Website

text

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Attachment to LER 80-009/01T-0 Rochester Gas and Electric Corporation R. E. Ginna Nuclear Power Plant, Unit No. 1 Docket No. 50-244 A program of planned Eddy Current examination was conducted on both steam generators (SG) "A" and "B" from May 7 to May 12, 1981 during the annual refueling and maintenance outage.

This examination consisted of multi-frequency Eddy Current Examination to detect and measure potential tube defects.

The inlets of both SG's received 100~a inspection and the outlets xeceived approximately 25'o inspection.

The results of the Steam Generator examinations did not reveal any reportable indications in the outlets of either steam generator and the inlet of the "A" Steam Generator.

After a final review of the data from the "B" Steam Generator inlet 14 tubes showed crevice indication and one tube had a pluggable defect above the tube sheet near the periphery.

Five (5) of the 14 crevice indications were above the plugging criteria, and of these 5 only 2 showed any growth during the last reactor operating period.

The cause for these crevice indications is a caustic attack occurring in the tube sheet crevices.

This caustic condition is a result of the changing Na/PO< molar ratio that has been occurring in the crevice areas since the conversion to all volatile treatment (AVT).

A program of crevice flushing has been conducted three (3) times over the last reactor operating year for a total of 68 cycles of flushes.

These flushes resulted in removal of Na and PO< from the crevices.

The one defect found in the periphery is associated with the mechan-ical problem in the number 0 wedge area of the "B" steam generator, Thirteen (13) of these 14 crevice indications were sleeved, one was pulled'or examination, and the one in the periphery area showing defect was plugged.