ML20149D445
| ML20149D445 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 02/04/1988 |
| From: | Beck J, Counsil W TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| CP-85-53, TXX-88125, NUDOCS 8802090497 | |
| Download: ML20149D445 (2) | |
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MFE Log # TXX-88125
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File # 10110 r
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903.8
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1UELECTRIC U,IuTAN,U.,
February 4, 1988 U. S. Nuclear Regulatory Commission Attn:
Document Control Desk Washington, D.C.
20555
SUBJECT:
COMANCHE PLAK STEAM ELECTRIC STATION DOCKET N0. 50-445 SEISHIC CATEGORY I PLATFORMS SDAR: CP-85-53 (FINAL REPORT)
Gentlemen:
On December 20, 1985, we verbally notified your Mr. R. Hall of a deficiency involving Seismic Category II platforms. On June 19, 1987, we notified you via TXX-6524 that the deficiency only involved a Seismic Category I platform.
Our last interim report on this issue was logged TXX-7113, dated December 18, 1987. We have concluded that this condition is reportable under the provisions of 10CFR50.55(e).
The required information follows.
DESCRIPTION OF DEFICIENCY Originally this deficiency was identified as encompassing several platforms which were not fabricated in accordance with prescribed design documents.
After further evaluation, we have confined this issue to a single Seismic Category I platform located at elevation 792' in the Reactor Containment Building.
The cause of this deficiency was determined to be inadequate inspection precedures and inadequate construction supervision.
The result was an unfinished platform with incomplete QC inspections.
The implication of this finding applies to the total population of structural steel with missing iimpection documentation and is addressed by CAR 87-012 and associated SDAR CP-87-71, "Missing Welds and Undersized Members."
SAFETY IMPLICATIONS Failure of this n'atform during a seismic event could have resulted in a loss of attached safety related instrument lines csulting in loss of associated control / indication functions.
The condition represents a significant deficiency in construction requiring extensive evaluation / repair to establish the adequacy of this platform to remain intact during a seismic event.
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I TXX-88125 February 4,1988
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Page 2 of 2 CORRECTIVE ACTION The corrective action for this issue is enveloped by the corrective actions for SDAR CP-87-71 and is listed below.
"Seismic Category I and 11 structural steel assemblies for which inspection are not available will be reworked in accordance with the applicable design drawings.
The reworked assemblies will be inspected in accordance with QI-QP-11.14-1, "Inspection of Site Fabrication and Installation of Structural and Miscellaneous Steel." Any discrepancies l
will be documented and dispositioned using Nonconformance Reports (NCRs)."
This is our final report on this issue.
Preventive action, and notification of completion of corrective actions will be provided in response to SDAR CP-87-71, which is scheduled to be submitted no later than March 2, 1988.
Very truly yours, W. G. Counsil By: hft), bc JcWn W. Geck Vice President, Nuclear Engineering l
JCH/grr i
c-Mr. R. D. Martin, Region IV l
Resident Inspectors, CPSES (3) i l
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