ML20137H724

Final Part 21 & Deficiency Rept 84-10 Re Wall Thickness Inadequacies for Small Bore ASME Class Ii,Iii & Class H Piping.Initially Reported on 840720.Util & Sargent & Lundy Program Verified Acceptability of safety-related Piping Sys

ML20137H724
Person / Time
Site:	Braidwood
Issue date:	01/07/1986
From:	Delgeorge L COMMONWEALTH EDISON CO.
To:	James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
REF-PT21-86-062-000 1093K, 84-10, PT21-86-062-000, PT21-86-62, NUDOCS 8601210641
Download: ML20137H724 (2)

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/n.'N Commonwealth Edison }I l} &

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O Address Reply to: Post Office Box 767

• ' (sg]) One First National Plaza. Chicigo. llhnois Chicago. ;tlinois 60690 January 7, 1986 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 Final Report Piping Wall Thickness Deficiencies NRC Docket Nos. 50-456/457 Reference (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 (d): D.H. Smith letter to J.G. Keppler dated December 13, 1984 (e): D.H. Smith letter to J.G. Keppler dated February 27, 1985 (f): A.D. Miosi letter to J.G. Keppler dated May 2, 1985

Dear Mr. Keppler:

References (a) thru (f) provided information concerning a deficiency reportable pursuant to 10 CFR 50.55(e) regarding wall thickness inadequacies for small bore ASME Class II, III and Class H Piping at our Braidwood Station. The purpose of this letter is to inform you the corrective actions identified by Commonwealth Edison to address this issue are now complete. This is considered to be a final report. As previously identified, the corrective action program was developed by Commonwealth Edison and Sargent and Lundy (S&L) to verify the acceptability of installed 2 inch and under safety-related piping systems at Braidwood Station. It has been demonstrated through this action that the pipe has adequate strength to perform its intended design function for the life of the plant.

B601210641 860107 PDR ADOCK 05000456 s PDR JAN 101996 1 1A R2]

The attached report (Engineering Evaluation of the Pipe Corrosion Problem Identified in CECO. NCR 633) has been prepared which provides the basis for acceptability of the installed pipe.

One signed original and three copies of this letter and the attachments are submitted for your use. An additional distribution of this Report is expected within five (5) working days. That distribution will include twenty additional bound copies of this Report for your use as well as 5 copies of the Report to both the Office of Nuclear Reactor Regulation and your headquarters office.

Very truly yours, Louis O. DelGeorg l Assistant Vice-President 4

/klj Attachments cc: H.R. Denton (NRR)-w/o attachmento J.M. Taylor (I&E)-w/o attachments I

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