JPN-90-057, Forwards GE Supplemental Rept of Ultrasonic Indications in Top Head Weld VC-TH-1-2 at Ja Fitzpatrick Power Station

Forwards GE Supplemental Rept of Ultrasonic Indications in Top Head Weld VC-TH-1-2 at Ja Fitzpatrick Power Station

ML20063Q021
Person / Time
Site:	FitzPatrick
Issue date:	08/14/1990
From:	Brons J POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20063Q022	List: JPN-90-057, Forwards GE Supplemental Rept of Ultrasonic Indications in Top Head Weld VC-TH-1-2 at Ja Fitzpatrick Power Station ML20063Q024
References
JPN-90-057, JPN-90-57, NUDOCS 9008170021
Download: ML20063Q021 (2)

Text

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*123 Mein Street . '

White Pbins.NewYork 10601 ;

o' i. _ 914 681.0240 ,-__

M g' -

John C. Cnms E mecutive Vice President .

Nucicat Generation l

August 14,1990 -  !

. JPN 90-057 1 U.S. Nuclear Regulatory Commission )

Attn: Document Control Desk Mall Stop P1 137 -

Washington, DC 20555 l l

Subject:

James A. RtzPatrick Nuclear Power Plant Docket No.'50-333 Reactor Vessel Head 1 Supplemental Report on Plate Segregates ,

References:

1. NYPA letter, J. C. Brons to NRC dated May 25,1990 (JPN 90-040) .

regarding reactor vessel head flaw indication inspections and analyses.  ;

2. NRC letter, D.E.1.aBarge to J.C. Brons dated June 13,1990 regarding _  ;

evaluation of reactor vessel head flaw.

Dear Sir:

d Authority engineers met with the NRC staff on May 17,1990 to discuss indications identified - )

during routine inservice inspections of the FitzPatrick reactor vessel bead. welds. The Authority prepared a report (Reference 1) that summarized these inspections and analyzed two of the vessel head indications identified during the inspections. These analyses conservatively assumed that the indications were crack 3 despite evidence to the contrary. The Authority concluded that these indications were attrSutable to metallic inclusions (also known as plate segregates) and that operation with the indicrAon was not a safety concern. An NRC evaluation (Reference 2) concurred with this ccnclusion.

In Reference 1, the Authority committed to prepare and submit a second report detailing the effects of segregates on non-destructive ultrasonic examinations. A copy of that report is -

attached. The report sumrnarizes the results of tests performed a material known to contain -

segregates and similar to that used in the FitzPatrick head, it supports tis .^'.dhority's earlier '

conclusion that refracted longitudinal waves alone cannot be used to distinguish between segregates and a flaw. Inspectors can use shear waves in conjunction with longitudinal waves and other non-destructive examination techniques to confirm or deny the presence of segregates.

9008170021 900814 "

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gDR ADOCK 05000333 l

, PDC n 1

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, . i The Authority will reinspect the reactor vessel head during the next three refueling outages as requested by the staff in Reference 2. If significant changes in the size or charactor of the flaw are detected during those three inspections, a report summarizing the inspection and an analytical evaluation will be prepared and submitted to the NRC staff for review prior to startup. If no significant changes are detected, a special report or analysis is not required and the inspection results will be documented at part of the standard Inservice inspection Program.

If you should have any questions please contact Mr. J. B. Ellmers.

Very truly yours, C Ys' ccutive Vice President

, Nuclear Generation cc: Regional Administrator

, U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Office of the Resident inspector U. S. Nuclear Regulatory Commission P. O. Box 136 Lycoming, NY 13093 Mr. David E. LaBarge Project Directora'c '-1 Division of Reacot .>rojects -l/II U. S. Nuclear Regulatory Commission Mail Stop 14 B2 Washington, DC 20555 i

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