TXX-5029, Interim Deficiency Rept CP-84-12 Re Environ Qualification of Equipment Outside Containment for High Energy Line Breaks. Initially Reported on 860604.Next Rept Will Be Submitted by 861024

Interim Deficiency Rept CP-84-12 Re Environ Qualification of Equipment Outside Containment for High Energy Line Breaks. Initially Reported on 860604.Next Rept Will Be Submitted by 861024

ML20215A788
Person / Time
Site:	Comanche Peak
Issue date:	09/19/1986
From:	Counsil W, Keeley G TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To:	Johnson E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
References
CP-84-12, TX-5029, TXX-5029, NUDOCS 8610060239
Download: ML20215A788 (1)

Text

Log # TXX-5029 File # 10110 903.11 TEXAS UTILITIES GENERATING COMPANY SKYWAY TOWER . 400 NORTH OIJVE STREET, L.B. M1. DALLAN. TEXAS 75201 September 19, 1986 W

.. ILU-A M. .G.. C.OU.N.S.I.L, Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects _ l U.S. Nuclear Regulatory Commission i S[P 2 b j933 '

611 Ryan Plaza Drive, Suite 1000 , 'j j Arlington, TX 76012 _

1

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NOS. 50-445 AND 50-446 IMPACT OF HELB TEMPERATURES ON QUALIFIED EQUIPMENT OUTSIDE CONTAINMENT SDAR: CP-84-12 (INTERIM REPORT)

Dear Mr. Johnson:

On June 4,1984, we verbally notified your Mr. D. Hunnicutt of a deficiency involving the environmental qualification of equipment outside containment for high energy line breaks (HELB). This is an interim report of a potentially reportable item under provisions of 10CFR50.55(e). Our most recent interim report was logged TXX-4912, dated July 16, 1986.

The course of our evaluation has included the plant specific application of the unreviewed safety question investigated by the Westinghouse Owners Group involving the thermal analysis of the environment, and the effects of superheated steam on the operability and qualification of Class 1E components.

Currently, these efforts have been completed with the exception of an analysis to determine the cable sheath temperature inside conduits in the break compartments during the line break scenario. A schedule for completion of this analysis is expected October 3, 1986.

We are continuing our evaluation of this issue and anticipate submitting our next report by October 24, 1986.

Very truly yours, W. G. Co n il By:

8610060239 e60919 G. 5. Keeley_ /

gDR ADOCK 0500 5 Manager, Liceh 'ng JCH/amb j c - NRC Region IV (0 + 1 copy) l Director, Inspection & Enforcements (15 copies)

U. S. Nuclear Regulatory Commission Washington, D.C. 20555 is a mvusws or rexas ununes us.ecrme cow aur g,g7

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