ML20043E891

Forwards IGSCC Insp 1990 Refueling Outage Summary Rept Addendum

ML20043E891
Person / Time
Site:	FitzPatrick
Issue date:	06/07/1990
From:	Brons J POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
JPN-90-044, JPN-90-44, NUDOCS 9006130495
Download: ML20043E891 (5)

Text

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- + :123 Main Street

. Whi te P,lains, NewYork 10601.

!,a. ., 914 681.6240 h gh.khgf; John C. Brons Executive Vice President

& Orlty: Nuclear Generation .

June 7 ,1990 JPN 90 044 U. S. Nuclear Regulatory Commission

! Attn: Document Control Desk

, Mall Stop P1137 Washington, D. C. 20555

Subject:

James A. RtzPatrick Nuclear Power Plant Docket No. 50-333 IGSCCinspection . .

1990 Refueling Outage Summary ReportIJdendum

Reference:

1. NYPA letter, J. C. Brons to NRC, dated May 25,1990 (JPN 90 041), "lGSCC Inspection 1990 Refueling Outage Summary Report."

Dear Sir:

In Reference 1 the Authority reported the results of intergranular stress corrosion cracking (IGSCC) inspections performed during the 1990 refueling outage. Of the eight weld overlays required during this outage, one overlay has been determined to be slightly undersized. That is, the thickness is less than that required by NUREG-0313 Revision 2 for a standard overlay. The Authority, therefore, performed an engineering evaluation to demonstrate acceptability.

Attachment 1 summarizes the as-built inspection results and the results of the evaluation.

Should you or your staff have any questions regarding this matter, please contact Mr. J. B. Ellmers of my staff.

Very truly yours, o!EG. Brons Executive Vice President Nuclear Generation Attachment cc: See next page 9006130495 900607 PDR ADOCK 05000333 \ g Q PDC

3 2 l References 1.. NYPA letter, J. C. Brons to NRC, dated May 25,1990 (JPN 90041), "lGSCC Inspection 1990 Refueling Outage Summary Report."

2. Structural Integrity Associates, Inc. letter, H. Gustin to NYPA/R. Penny (HLG-90-020), dated '

May 21,1990, regarding evaluation of as built weld overlay thickness on weld 28-02 2-33.

3. Structural Integrity Associates, Inc. letter, H. Gustin to NYPA/R. Penny (HLG-90-024), dated May 25,1990, regarding evaluation of as-built weld overlay thickness on weld 28 33 using source equations..

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,lrgroduction The Authority inspected the overlay on Reactor Water Reciruulation System weld 28 33 in the as-built condition. It was determined that the overlay was slig'itly undersized when compared to NUREG-0313 Revision 2 design guide;ines for a standard overlay. An evaluation was performed to justify the aa-bu!M thickness.

Inspection Results As is standard practice, the as-built thicknesses of the weld overlays were verified by ultrasonic measurements. Four readings were taken in each of four quadrants 90 degrees apart. The following data was recorded for this weld overlay.

Baseline Readings Prior After Surface As built Thickness to Weld Overlay Finishing of Weld Overlay (in.) (in.) (in.)

1.429 1.975 0.546 1.430 1.950 0.520 1.429 1.943 0.514 1.429 2.010 0.581 Average 0.540 Note: Readings are the average of four readings for each quadrant.

Evaluation l

The design thickness of the overlay for weld 28-33 was 0.54*. As indicated above, two quadrants did not meet this value. The Authority contracted Structural Integrity to evaluate the overlay on weld 28-33. Two analyses (References 2 and 3) were performed with both showing acceptable results. The analyses examined the conservatisms in the original overlay design and evaluated i the overlay thickness using the source equation methodology as presented in Appendix C to l ASME Section XI. I l A review of conservatisms in the overlay design showed that the pipe thickness used in the l

! evaluation was 1.53' whereas the actual thickness of the pipe is 1.43". If 1.43' had been used as ,

I the pipe thickness, the overlay design thickness would have been 0.512" which is less than the minimum measured thickness. Additionally, the overlay design used an allowable stress of 15,900 psi instead of the code allowable 16,950 psl which resulted in a thicker overlay design.

Use of the source equation methodology presented in Appendix C of ASME Section XI calculates j a reinforcement thickness of 0.41' with a final weld overlay dimension ratio, a/t, of 0.79".

Paragraph C 3320d of ASME Section XI limits the final a/t to o 75' which results in a repair thickness of 0.51' which again is less than the minimum measured thickness.

Through the performance of the above evaluations,-it has been determined that the as built dimension of the weld overlay for weld 28-33 is acceptable.

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ATTACHMENT 1 to JPN 90 044 ADDENDUM TO

SUMMARY

OF INTERGRANULAR STRESS CORROSION CRACKING INSPECTION DURING 1990 REFUEUNG OUTAGE x.

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.I NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 i

cc: Office of the Resident inspector U. S. Nuclear Regulatory Commission Post C4fice Box 136 Lycoming, New York 13003 Regional Administrator

. U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, Pennsylvania 19406 Mr. David E. l.aBarge Project Directorate 11 Division of Reactor Projects 1/11 U. S, Nuclear Regulatory Commission Mall Stop 14 B2 Washington, D. C. 20555 Mr. R. McBrearty U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, Pennsylvania 19406

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