ML20127G797
| ML20127G797 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 05/02/1985 |
| From: | Miosi A COMMONWEALTH EDISON CO. |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| 0060K, 60K, 84-10, NUDOCS 8505210147 | |
| Download: ML20127G797 (2) | |
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/ N Commonwealth Edison'.
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/ Chicago Illinois 60690 May 2, 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, 1964 (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
Dear Mr. Keppler:
References (a) thru (e) 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 '1etter 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.
A corrective action program was developed by Commonwealth Edison Company and Sargent & Lundy to. disposition the subject pipe that has been installed.
The corrective action program includes the following elements:
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1.1 L'aboratory testing to verify,the design significant properties of the suspect pipe.
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'I2.- LAnalhsistoevaluatetheeffect'ofprolongedoutdoor
~~ storage'and sub'sequentfchemical cleaning.
3.'
. Measurement.of.the actual. wall thickness' of samples of
. suspect pipe taken from both installed. pipe'and pipe on-1 hold.in storage.
-4.
' Analysis of laboratory testing results and pipe-wall thicknessimeasurements 'to determine: the acceptability of installed! piping relative to'ASME Section III design
_requirenents.
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..-Resulks of the laboratory tests on:the. suspect pipe are
'l currently being evaluated by Sargent & Lundy for design significance.
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'An inventory of. suspect pipe installed in the plant and on'
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- holo in~ storage has been completed.
Based on a-total of approximately.:28,700 piecesi a random. sample'of 300: pieces has been fselected.for detailed measurement.
This-sample size wasJselected to d
1 satisfy a 95%! confidence /99% reliability criterion.- Work is-
- presently: underway,.in accordance with Phillips Getschow Co.
- Procedure PGCP-52,Lto-measure the wall thickness:of this sample.
! Current: estimates' indicate the sample measurements are expected to?
'be(completed by July-1, 1985.
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.JO final report, covering the' analysis of laboratory
~ testing,) pipe wall measurements, and effects of prolonged outdoor
.i storage:and subsequent chemical cleaning is expected to-be. completed-lby: August, 1985.
Please address any questions that you or your staff'may have.concerning this matter to this office.
Very truly-yours, I
d
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Anthon D. Miosi Nuclear Licensing Administrator
/klji cc:. NRC~ Resident. Inspector - Braidwood
.q Director of Inspection.and_ Enforcement-U.S.' Nuclear Regulatory Commission Washington, D.C. 20555 j
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