ML20099G974

Interim Deficiency Rept 84-10 Re Wall Thickness Inadequacies for Small Bore ASME Class II Piping.Lab Testing of Pipe Samples in Progress.Next Rept Will Be Submitted by 850501

ML20099G974
Person / Time
Site:	Braidwood
Issue date:	02/27/1985
From:	Danni Smith COMMONWEALTH EDISON CO.
To:	James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
84-10, 9812N, NUDOCS 8503150134
Download: ML20099G974 (2)

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@ One First Rational Plaza. Chicago, lihnoi Commonwealth Edison Address Reply to: Post Office Box 767 Chicago, lilinois 60690 February 27, 1985 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 (d):

D.

H.

Smith letter to J. G. Keppler dated December 12, 1984

Dear Mr. Keppler:

References (a) thru (d) provided information concerning a deficiency reportable pursuant to 10 CFR 50.55(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 As previously reported, Commonwealth Edison Company NCR 633 (Rev. 1) was written to track issue resolution.

All suspect pipe in storage has been placed on hold pending the dispositioning of installed pipe.

EO L

B503150134 850227

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PDR ADOCK 05000456 S

PDR

J. G. Keppler February 27, 1985 1

A corrective action program is being developed by Commonwealth Edison Company and Sargent & Lundy to disposition the subject pipe that has been installed.

The proposed corrective action program includes the following elements.

1.

Laboratory testing to verify the design significant properties of the suspect pipe.

2.

Analysis to evaluate the effect 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 and pipe on hold in storage.

4.

Analytical analysis of laboratory testing results and pipe l

wall thickness measurements to determine the acceptability of installed piping relative to ASME Section III design requirements.

Laboratory testing of pipe samples is presently underway with completion expected by the end of February.

Suspect pipe installed in the plant and on hold in storage is presently being inventoried for sample selection and subsequent wall thickness measurement.

A corrective action completion schedule has not been finalized at this time.

Consequently, an interim report updating the status of issue resolution will be submitted by May 1, 1985.

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

Very truly yours, David H. Smith Nuclear Licensing Administrator cc:

NRC Resident Inspector - Braidwood Director of Inspection-and Enforcement U.S. Nuclear Regulatory Commission Washington,'D.C. 20555 9812N s.