ML20083Q769
| ML20083Q769 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 04/12/1984 |
| From: | Hall D ILLINOIS POWER CO. |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| 1605-L, 55-83-08, 55-83-8, U-10141, NUDOCS 8404230240 | |
| Download: ML20083Q769 (2) | |
Text
"
b/h13 1
I
~
ILLINDIS POWER COMPANY l
500 SOUTH 27TH STREET, DFCATUR, ILLINOIS 62525
(
April 12, 1984 I
i Docket No. 50-461 Mr. James G. Keppler Regional Administrator Region III U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137
Subject:
Potential Deficiency 55-83-08 10CFR50.55(c)
Damage to Guard Pipe Bellows Assemblies
Dear Mr. Keppler:
7 J
On June 27, 1983, Illinois Power notified Mr. F. Jablonski, NRC Region III (Ref IP Memorandum Y-17131, 1605-L, dated June 29, 1983) of a potentially reportable deficiency per 10CFR50.55(e)Econcerning construction damage to guard pipe bellows assemblics.
This initial notification uns followed by two (2) interim reports (Ref: IP letter U-10077, D. P. Hall to J.
G. Keppler dated August 16, 1983, and IP letter U-10113, D. P.
Itall to J. G. Keppler dated December 15, 1983).
Our investigation of this matter continues, and this letter represents an interim report per 10CFR50.55(c).
Statement of Potentially Reportable Deficiency Ten (10) guard pipe bellows assemblies used at Clinton Power Station (CPS) were damaged ciuring installation and construction activities.
This damage consists of small dents, nicks, scratches, and are strikes, with one (1) assembly exhibiting a small hole in one (1) of the two (2) bellow plys.
An evaluation of this issue is being performed to determine the consequences of this damage and necessary actions to make the bellows acceptable.
l Background / Investigation Results/ Corrective Action During installation of the guard pipes and associated bellows assemblies, eleven (11) Nonconformance Reports (NCRs) were written to document cases of damage to ten (10) of eleven (11) bellows assemblies.
These bellows assemblies, anchored to the drywell wall and welded to the guard pipu, act as a seal isolating the drywell environment while allowing free axial thermal and seismic movement of the guard pipe.
The bellows assemblies are not pressure retaining parts of either the reactor or the primary containment, but were fabricated, tested, and certified in accordance with the ASME Code,Section III, M0 APR 1619M o
Tod
Mr. Jamos G. Kcppler Pago 2 April 12, 1984 Subsection NE (Class MC), to take advantage of available code specifications.
The original supplier of tbc bellows assemblics is no longer in this type of business.
An evaluation of this problem is being performed to determine the remedial actions necessary to establish the acceptability of the damaged bellows.
Several methods are beinF pursued, which include testing of a prototype bellows assembly and repair of the presently installed bellows.
Pathway Bellows, Inc., was awarded the contract to perform testing of the prototype bellows assemblics and to supervise repairs, if required.
A completed test report is scheduled to be submitted to Illinois Power and Sargent & Lundy by June 1, 1984, and is expected to justify a "use-as-is" disposition for most of the minor dents and scratches.
The classification of the bellows assemblics was also revised from ASME to ANSI B31.1 to facilitate any repairsi however, they have retained their safety related, seismic Category I classification.
To prevent further damage, the installed bellows assemblies have been covered with protective coverings.
Safety Implications / Significance The consequences of the damage to the installed bellows is not known at this time.
Further evaluation of the issue is necessary to determine the significance of the damage and the need for repair or replacement of the assemblies.
It is expected that remedial action will not be necessary on most of the minor dented and scratched bellows.
The evaluation of this issue has required an extended period of time to complete.
Illinois Power expects to provide a final report on this issue in approximately one hundred twenty (120) days.
We trust that this interim report provides you sufficient background information to perform a general assessment of this potentially reportable deficiency, and adequately describes our overall approach to resolve the problem.
Sincerely yours, D.
2 Hall Vice President RDW/ lag cc NRC Resident Office Director - Office of I&E, USNRC, Washington, DC 20555 1111nois Department of Nuc1 car Safety IMPO Records Center