05000272/LER-1980-055, Forwards LER 80-055/01T-0

Forwards LER 80-055/01T-0

ML18085A261
Person / Time
Site:	Salem
Issue date:	11/14/1980
From:	Librizzi F Public Service Enterprise Group
To:	Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML18085A262	List: 05000272/LER-1980-055, Forwards LER 80-055/01T-0 05000272/LER-1980-055-01, /01T-0:on 801029,unfused Area Found in Root Portion of Butt Weld on Steam Generator 13.Caused by Weld Defect in 1979 Repair.Nondestructive Testing Base Line Data Will Be Completed Before Unit Returned to Svc
References
NUDOCS 8011200291
Download: ML18085A261 (3)

LER-1980-055, Forwards LER 80-055/01T-0

Event date:
Report date:
2721980055R00 - NRC Website

text

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PS~G Public Service Electric and Gas cl*§~l~~~mt~~ewark. N.~. 07101 Phone 201 430-7000 Mr. Boyce H. Grier Director of USNRC 1980' MOV' 20 J!.M 9 2 t November 14, 1980 Off ice of Inspection and Enforcement Region 1 631 Park Avenue King of Prussia, Pennsylvania 19406

Dear Mr. Grier:

LICENSE NO. DPR-70 DOCKET NO. 50-272 REPORTABLE OCCURRENCE 80-55/0lT Pursuant to the requirements of Salem Generating Station Unit No. 1 Technical Specifications, Section 6.9.1, we are submitting Licensee Event Report* for Reportable Occurrence 80-55/0lT.

This report is required within fourteen (14) days of the occurrence.

Sincerely yours,

/tJ(L f;_f:*. r'.'u#'?,,( JV General Manager -

Electric Production CC:

Director, Office of Inspection and Enforcement (40 copies)

Director, Office of Management Information and Program Control (3 copies) 95.::>001 1200\\-11 2*78

Report Number:

Report Date:

Occurrence Date:

Facility:

ao-sA1T 11/14/80 10/29/80 Salem Generating Station, Unit 1 Public Servcie Electric & Gas Company Hancocks Bridge, New Jersey 08038

~DENTIFICATION OF OCCURRENCE:

Linear Discontinuity Discovered in No. 13 Steam Generator Feedwater Nozzle to Elbow Weld CONDITIONS PRIOR TO OCCURRENCE:

Mode 6 -

Refueling Operations DESCRIPTION OF OCCURRENCE:

During volumetric examination of the Steam Generator Feedwater Nozzle to pipe fitting weldments on Nos. 11, 12 13 and 14 Steam Generators, a linear indication was found in weld No. FW1-SGF-66~P2 at No. 13 Steam Generator.

Radiography showed a linear discontinuity approximately l" long appearing to be an unfused area in the root portion of the butt weld on the elbow side.

Ultrasonic examination revealed the presence of this same indication with a suspicious area continuing for a total of 6 to 7 inches that was recordable but because of geometric discontinuities in the area, the indication could not be identified.

Using radiography and. dye. penetrant to locate an'd follow the dis-continuity, the area of the indication was evacuated.

Weld repair was made using similar materials and welding procedures as were used duiing construction of the plant.

DESIGNATION OF Al'PARENT CAUSE OF OCCURRENCE:

Lack of fusion in the 1979 weld repair.

ANALYSIS OF OCCURRENCE:

During the 1979 refueling, the weldments and adjoining base material were given a complete radiographic and ultrasonic examination in response to NRC Bulletin 79-13 revealing circumferential cracks in all four loops which were subsequently repaired (LER 79-46).

As part of the.ongoing program, follow-up examination performed during the current refueling outage identified the present indication on NO. 13 Steam Generator.

Based on volumetric nondestructive examination, it was determined that the linear discontinuity did not meet the con-struction code ANSI B31.7.

Further, it was not similar to the issue addressed by the NRC Bulletin 79-13 but rather a lack of fusion in the 1979 weld repair.

The decision was made to locally remove the indication and repair the weldment.

LER 80-55/0lT

..,. 2 -

CORRECTIVE ACTION

Repair welding was accomplished using a manual GTAW open root technique with two layers of manual GTAW deposit on top of the root.

This root portion was then PT and RT examined with no reportable indications found.

SMAW was used to complete the weld.

The com-pleted weld was post weld heat treated in accordance with ANSI B31.7.

Upon completion of post weld heat treatment and blending, final RT and PT wa.s completed.

UT base line data will be undertaken prior to the unit's return to service.

FAILURE DATA:

Not Applicable Prepared By J. M. Randolph SORC Meeting No.

95-80