ML20214G096

Interim Deficiency Rept 87-09 Re Linear Indication Identified on Reactor Vessel Weld During Preservice Insp Exam.Initially Reported on 870401.Westinghouse in Process of Analyzing Boat Sample.Addl Rept Expected by 870630

ML20214G096
Person / Time
Site:	Beaver Valley
Issue date:	05/01/1987
From:	Sieber J DUQUESNE LIGHT CO.
To:	Murley T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
2NRC-7-103, 87-09, 87-9, NUDOCS 8705260415
Download: ML20214G096 (3)

Text

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'Af M 2NRC-7-103 Beaver Valley No. 2 Unit Project Organization Telecopy ) 643-52 Ext.160 I.$.BolS$$"' May 1, 1987 Shippingport, PA 15077 United States Nuclear Regulatory Commission Region I 631 Park Avenue King of Prussia, PA 19406 ATTENTION: Dr. Thomas E. Murley Administrator

SUBJECT:

Beaver Valley Power Station - Unit No. 2 Docket No. 50-412 Linear Indication Identified on Reactor Vessel Weld During PSI Examination Potential Significant Deficiency Report 87-09, Interim Report Gentlemen:

This Potentially Reportable Significant Deficiency Report is being submitted pursuant to the requirements of 10CFR50.55(e). It is anticipated that an additional report will be issued by June 30, 1987.

DUQUESNE LIGHT COMPANY By

// J. D. Sieber

(/ Vice President Nuclear LMR/ijr NRC/LMR/SDR/8709 Attachment AR/NAR cc: Mr. P. Tam, Project Manager (w/a)

Mr. J. M. Taylor, Director (3) (w/a)

Mr. J. Beall, Sr. Resident Inspector (w/a)

Mr. L. Prividy, NRC Resident Inspector (w/a)

INP0 Records Center (w/a)

NRC Document Control Desk (w/a) kp Q 2 s

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% ATTACHMENT

1. Summary During the performance of the Preservice Inspection (PSI) automated ultra-sonic test (UT) of the Reactor Vessel, an indication was found on the outside diameter (OD) on the longitudinal weld (weld #6) located above the loop 1 inlet nozzle. Subsequent surface examination from the OD using magnetic particle testing (MT) confirmed the indication.

2. Immediate Action Taken An Inservice Inspection Department (ISID) Deficiency Report and a Noncon-fonnance and Dispositon Report (N&D) were written.

Mr. L. M. Rabenau, Lead Compliance Engineer, Beaver Valley Power Station Unit No. 2, notified Mr. D. Limroth, NRC Region I, of this concern on April 1, 1987.

3. Description of Deficiency The PSI examination of the Reactor Vessel identified a 2 inch vertical linear indication on the 0. D. of the vessel at Weld #6, which is located above the loop 1 inlet nozzle. Additionally, three (3) 3/8 inch curvilinears and four (4) curvilinears of various lengths were also identified as a result of the MT.

4. Analysis of Safety Implication The results of tne UT appear to exceed ASME XI acceptance criteria, IWB Category B-A 1980 - Winter 1980.

5. Corrective Action To Resolve the Deficiency A " Boat" sample, approximately 4" long by 1" wide and .75 inches deep, was removed by Westinghouse NSTD for the vertical linear indication, and the area has been blended to meet the acceptance criteria of ASME XI, IWB Category B-A 1980 - Winter 1980. Ultrasonic and magnetic particle exami-nations confirmed removal of the indication.

Westinghouse R&D is in the process of analysing the " Boat" sample. Upon completion of the analysis, N&D 44035 will be final dispositioned. Any further action will be determined at that time.

6. Additional Reports It is anticipated that an additional report will be issued by June 30, 1987.