ML20101K724

Interim Deficiency Rept 84-10 Re Wall Thickness Inadequacies for Small Bore ASME Class II Piping.Initially Reported on 840720.Corrective Action Program Being Developed.Next Rept Due by 850215

ML20101K724
Person / Time
Site:	Braidwood
Issue date:	12/12/1984
From:	Danni Smith COMMONWEALTH EDISON CO.
To:	James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
84-10, 9518N, NUDOCS 8412310453
Download: ML20101K724 (2)

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'# D-f N Commonwealth Edison

) One First N'tional PPz9. Chicago. Ilknoi2

(  : 7 Address Reply to: Post Offica Box 767

\ , / Chicago, Illinois 60690 December 12, 1984 Mr. James G. Keppler

' Regional Administrator U. S. Nuclear Regulatory Commission Region III

-799 Roosevelt Road Glen Ellyn, IL 60137

Subject:

Braidwood Station Units 1 and 2 10 CFR 50.55(e) No. 84-10 Interim Report Piping Wall Thickness Deficiencies NRC Docket Nos. 50-456/457 References (a): E. D. Swartz letter to J. G. Keppler dated July 20, 1984 (b): D. H. Smith letter to J. G. Keppler dated September 18, 1984 (c): D. H. Smith letter to J. G. Keppler dated November 2, 1984

Dear Mr. Keppler:

References (a), (b) and (c) provided information concerning a deficiency reportable pursuant to 10 CFR 50.5S(e) regarding wall thickness inadequacies for small bore ASME Class II piping at our Braidwood Station. The purpose of this letter is to provide an updated status of the corrective actions taken to resolve this issue. This letter is considered to be an Interim Report.

Corrective Action Status y Commonwealth Edison Company NCR 633 (Rev. 1) has been written to track issue resolution. All suspect pipe in storage has

/ been placed on hold pending the dispositicning of installed pipe. A

l. / corrective action program is being developed by Commonwealth Edison l Company and Sargent and Lundy to disposition the subject pipe that has been installed. The proposed corrective action program includes the following elements.

, 1. 1.aboratory testing to verify the design significant properties of the suspect pipe.

2. ' Analysis to evaluate the affect of prolonged outdoor storage and subsequent chemical cleaning.

3. Measurement of the actual wall thickness of samples of suspect pipe taken from both installed pipe ano pipe on

-hold in storage.

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1 4' . Analytical analysis of laboratory testing results and pipe-wall thickness measurements to determine the acceptability of.

-installed piping relative to ASME Section III design requirements.

.A corrective action completion schedule has not been developed at this time. Consequently,-an interim report' updating the

).f status of issue resolution will'be submitted by February 15, 1984.

Please address any questions that you or your staff may have concerning this matter to this office.

Ver trulyry$urs, f

David H. Smith Nuclear Licensing Administrator cc: NTi0 Resident-Inspector - Braidwood

-)irector of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washingt<in, D.C. 20555 9518N

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