ML19327A840
| ML19327A840 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 10/05/1989 |
| From: | Stols R COMMONWEALTH EDISON CO. |
| To: | Murley T Office of Nuclear Reactor Regulation |
| References | |
| 0312T, 312T, NUDOCS 8910180238 | |
| Download: ML19327A840 (2) | |
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Commonwealth Edison 72 West Adams Stvet, Chichpo. Illinos ABdies ReiWiS~P6si Offiis B5i76F Chicago. Ilknms 60690 0767 October 5, 1989 Dr. Thomas E. Murley, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20SS5
Subject:
Quad Cities Station Unit 1 Intergranular Stress Corrosion Cracking Inspection Plar HRC_Dnthet No. 50-254 References (c):
Letter from T.H. Ross to T.J. Kovach dated June 6, 1989 (b):
Letter from R. Stols to T.E. Murley dated July 13, 1989 (c):
Letter from T.M. Ross to T.J. Kovach dated August 23, 1989 Dr. Murley Reference (a) transmitted the Safety Evaluation Report for Unit 1 Fall, 1987 IGSCC Inspection Plan and Repairs.
The Safety Evaluation Report contained a recommendation for Held 02M-S3 which was repaired with a leak barrier and fitted with a pipe lock in 1984.
In refernte (a), the NRC Staff indicated that the weld should be surfaced conditioned and ultrasonically examined during the next refueling outage to ensure effectiveness of the overlay and pipe lock in mitigating IGSCC.
Reference (b) transmitted additional information for the inspection method for Held 02M-53.
Ref erence (c) contained the results of the NRC Staff's review of reference (b).
Tha Staff identified some concerns with the Commonwealth Edison's justification for the weld inspection.
I On September 15, 1989, members of Commonwealth Edison and NRC Staff's conducted a conference call to achieve an acceptable method of inspection for weld 02M-53. Commonwealth Edison has agreed to remove the pipe lock on Unit 1 Recirculation Syrtem weld 02M-53 and conduct an ultrasonic examination of the leak barrier overlay.
A "best effort" ultrasonic examination will be
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Dr. T.E. Hurley October 5, 1989 performed, after surface conditioning, to ascertain the status of the existing axial orientated flaws reported during the Spring,1984 outage.
The ultrasonic examination will be performed by EPRI qualified ultrasonic examiners utilizing Commonwealth Edison approved procedures.
A decision to reinstall the pipe lock on Held 02H-53 will be made based upon the ultrasonic examination results.
The NRC Staff has agreed to consider an alternate inspection frequency for the pipe locked weld in the event of reinstallation of the pipe lock.
The NRC Staff concurred that no further Information is required, at this time, in response to the issues raised in reference (c).
Please direct any questions or comments on this topic to this office.
Very truly yours, J
R. Stols Nuclear Licensing Administrator cc:
A.B. Davis - Regional Administrator, RIII T.H. Ross - Project Manager, NRR H. Koo - NRR Senior Resident Inspector, Quad Cities 0312T:2
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