ML20155A590

Forwards Rev 1 to Vol 1 of SIR-88-018, Design Rept for Recirculation & RWCU Sys Evaluations & Repairs Performed During 1988 Refueling Outage..., Describing Flaws Found & Actions Taken Re IGSCC During Spring 1988 Piping Insp

ML20155A590
Person / Time
Site:	Quad Cities
Issue date:	06/01/1988
From:	Johnson I COMMONWEALTH EDISON CO.
To:	Murley T Office of Nuclear Reactor Regulation
Shared Package
ML20155A594	List: ML20155A590 ML20155A611
References
RTR-NUREG-0313, RTR-NUREG-313 4709K, NUDOCS 8806100148
Download: ML20155A590 (2)

Text

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[ Commonwealth Edison One Fird NTSonal Plan, Chica@o, Illinoie

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v 7 Address Reply to: Post Offc) Box 767

\ Chicago, Illinois 60690 0767 June 1, 1988 Mr. Thomas E. Murley, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555

Subject:

Quad Cities Station Unit 2 "Spring 1988 Inspection of piping Susceptible to Intergranular Stress Corrosion. Cracking (IGSCC)

NRC Docket No. 50-265

Dear Mr. Murley:

Commonwealth Edison is submitting a report detailing the results of the Quad Cities Unit 2 augmented piping inspection. This report provides a description of flaws found as well as the analytical and repair actions taken during the Spring 1988 refueling outage. The following two enclosures are provided:

1) Ultrasonic Examination of IGSCC susceptible Stainless Steel Weldments, Quad Cities Unit 2-1988 Refueling Outage.

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This enclosure provides a report of the ultrasonic examinations

! performed on IGSCC susceptible stainless steel weldments during the Quad l Cities Unit 2 refuel outage and provides a discussion on the following topics:

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• the "prioritization" study which was used to both select and schedule

[ weldments for UT examinations.

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• a description and UT examination history of welds which coritain IGSCC-like flaw indications.

• a comparison of the current UT examination results with those of the 1986 refueling outage for the weld overlay repairs examined during the 1988 refueling outage, and i

• a description of the repair activities to the end cap-to-header weld overlay repair performed last outage (02A-S10) which was evaluated as containg UT flaw indications.

i 8806100148 880601 a

PDR ADOCK 05000265 {

O DCD

T.E. Murley June 1, 1988

2) Design Report for Recirculation and Reactor Water Cleanup System Evaluations and Repairs performed during the 1988 Refueling Outage at the Quad Cities Nuclear Power Plant,. Unit 2, Structural Integrity Associates, Inc. Report No. SIR-88 018, vol, Revision 1, project No. Ceco - 090-1, May 1988.

This report documents the disposition and repair of flaw indications found by the examinations described in enclosure 1. All flaw evaluations and weld overlay repair designs were performed by Structural Integrity Associates, Inc. in accordance with NURBG-0313, Revision 2.

The weld overlay repairs are still in progress. Volume 2 of the Structural' Integrity Report will be submitted within 30 days after the end of the refuel outage and will include as-built weld overlay dimensions and the disposition of any flaw indications in weld overlays. The results of a system shrinkage stress piping analysis for the recirculation and RWCU piping, from we.1d overlay shrinkages, will also be documented in Volume 2. The results of this shrinkage stress analysis will be compared to the bounding shrinkage stress of 1 ksi assumed in Volume 1 for flaw evaluations in 28 inch recirculation system piping.

Please direct any questions you may have regarding this matter to  ;

this office.

J Ver ly yo ,

ir . Vh I. M. J n Nuclear Licensing Administrator im cc: T. Ross - NRR NRC Resident Inspector - Quad l

4709K l

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