JPN-90-075, Forwards Repts Detailing ISIs Performed During Spring 1990 Outage.Repts Include Intergranular Corrosion Cracking Insp Data,Reactor Pressure Vessel Weld Data & in-vessel Insp Data.W/O Encls

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Forwards Repts Detailing ISIs Performed During Spring 1990 Outage.Repts Include Intergranular Corrosion Cracking Insp Data,Reactor Pressure Vessel Weld Data & in-vessel Insp Data.W/O Encls
ML20065S789
Person / Time
Site: FitzPatrick Constellation icon.png
Issue date: 12/19/1990
From: Brons J
POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
JPN-90-075, JPN-90-75, NUDOCS 9012260060
Download: ML20065S789 (3)


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December 19,1990 JPN 90-075 i

U.S. Nuclear Regulatory Commission Attn: Document Control Desk l Mall Stop P1137 1 Washington, DC 20555 j

Subject:

James A. FitzPatrick Nuclear Power Plant Docket No. 50 333

- In Service inspection Summary Report Spring 1990 Outage (Reload 9/ Cycle 10)

References:

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

" Reactor Pressura Vessel Head Flaw Indication Inspections and Evaluation Analyses."

Dear Sir:

ASME Section XI requires submittal of an outage report to the NRC. The attached reports detail the FitzPatrick plant In Service inspections (ISI) performod during the Spring 1990 outage.

This submittal contains the following throo reports:

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1. " James A. FitzPatrick Nuclear Power Plant inservice Inspection of Components Spring 1990,"

Volumes I thru VI._ This report includes:

. - Intergranular stress corrosion cracking inspection data. . A total of 76 wolds were inspected,8 wclds required weld overlays where 7 overlays were for new IGSCC Indications, and I was for-a preexisting Indication;

. Erosion / corrosion data for inspections as required by IE Bulletin 87 01, " Thinning of Pipe Walls in Nuclear Power Plants" and Generic Letter 89-13, " Service Water System Problems Affecting Safety _Related Equipment."

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-9012260060 901219 OQ

-PDR ADOCK 05000333 l

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. 2. " James A. FitzPatrick Nuclear Power Plant Reactor Pressuro Vossol inservice Inspection Spring 1990," Volume 1. This report includes:

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. Reactor pressure vossel wold inspection data as required by ASME Section XI;

. The results of the main steam nozzle N 3C examination, which woro ;erformed using the GERlS system.

This report also documents the recont scheduled ISI examination during which the Authority identified flaws in the reactor pressure vossol head. The flaws were ovaluated using fracture mechanics, as recommondod in IWB 3122.4 and found to be acceptable for the continued operation of the plant until the next cycle. In Reforonce 1, the Authority reported the results from the ana'ysis to the NRC as required by IWB-3125. In lieu of the requirements of IWB 2420(b), "Roox6mination of flaws qualified as acceptable for continued service," the Authority will inspect th6so flaws during each of the next throo refueling outagos

3. " James A. FitzPatrick Nuclear Power Plant inservice Inspection of In Vossel Compononts Spring 1990," Volume I. This report consists of:

. Reactor in vossolinspection data as required by ASME Section XI. This portion of the report describes the inspections requestod by lE Bullotins 80-07, " Jet Pump Assembly Failure" and 8013, " Cracking In Core Spray Spargers."

If you have any questions, please contact Mr. J. A. Gray, Jr.

Very truly yours, l Alohn C. Brons Executive Vice President

[d uclear Gonoration N

cc: soo next pago

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. 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 Directorate 11' Division of Reactor Projects l/Il .  !

U. S. Nuclear Regulatory Commission Mall Stop 14 B2 "

Washington, DC 20555 Mr. Charles Lazart -

Hartford Steam Boller and Insurance Co.

Hartford Branch Office

-One State Street Hartiord, Connecticut 061019990

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