ML20147F495

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Supplemental Deficiency Rept CP-87-22 Re Impact Testing of Matls Attached to Containment Liner Not Implemented. Initially Reported on 871027.Correct Number for Design Change Authorization Is DCA 49098 Not DCA 49089
ML20147F495
Person / Time
Site: Comanche Peak  Luminant icon.png
Issue date: 03/04/1988
From: Beck J, Counsil W
TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
CP-87-22, TXX-88279, NUDOCS 8803070363
Download: ML20147F495 (1)


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log # TXX-88279 L

4 File i 10110

-Z 903.8 Ref.#10CFR50.55(e) tilELECTRIC l

If,'",?;fn March 4,-1988 U. S. Nuclear Regulatory Commission Attn: Document Control Oesk Washington, D.C.

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SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION DOCKET NOS. 50-445 AND 50-446 i

LINER ATTACHMENT MATERIAL REQUIREMENTS:

IMPACT TESTING SDAR: CP-87-22 (SUPPLEMENTAL REPORT)

Gentlemen:

On October 27, 1987, we notified you via our final report logged TXX-6908 of a deficiency which we concluded to be not reportable under the provisions of 10CFR50.55(c) wheroin FSAR (Section 3.8.1) and Specification (2323-55-14) 1 requirements regarding impact testing of materials attached to the containment ilner have not been implemented.

The purpose of this supplemental report is to correct a typographical error made in our final report.

Specifically, the Design Change Authorization (DCA) number utilized to modify Specification 2323/SS-14 was stated as DCA 49089.

The correct number is DCA 49098.

Very truly yours, W. G. Counsil By: b^%),/b>

Jotg W. Beck Vice President, Nuclear Engineering j

BSO/grr c-Mr. R. D. Martin, Region IV Resident inspectors, CPSES (3)

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