TXX-6067, Interim Deficiency Rept CP-86-70 Re Elevated Temp Effects on Instrument Supports & Tubing.Initially Reported on 861002. Tubing Currently Designed & Installed Using Max Operating Temp Criteria of 122 F.Next Rept Expected by 870116

Interim Deficiency Rept CP-86-70 Re Elevated Temp Effects on Instrument Supports & Tubing.Initially Reported on 861002. Tubing Currently Designed & Installed Using Max Operating Temp Criteria of 122 F.Next Rept Expected by 870116

ML20215N717
Person / Time
Site:	Comanche Peak
Issue date:	10/29/1986
From:	Counsil W TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To:	Johnson E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
References
CP-86-70, TXX-6067, NUDOCS 8611070193
Download: ML20215N717 (1)

Text

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Log # TXX-6067 File # 10110 903.11 TEXAS UTILITIES GENERATING COMPANY SEYWAY TOWEE . 400 NOftt,6 OLlVE drTREET. I.S. 98 . DAIJAS TEXA5 76305 i

October 29, 1986 ' '

"2#,5tfaW E @ -b i' NOV 4 1986 i :i Mr. Eric H. Johnson, Director L U Division of Reactor Safety and Projects U. S.~ Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000

' Arlington, TX 76012

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NOS. 50-445 AND 50-446 ELEVATED TEMPERATURE EFFECTS ON INSTRUMENT SUPPORTS AND TUBING SDAR: CP-86-70 (INTERIM REPORT)

Dear Mr. Johnson:

On October 2,1986, we verbally notified your Mr. I. Barnes of a potential deficiency regarding elevated temperature effects on instrument supports and tubing. This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e). 1 )

3

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A design assessment review has identified a concern relating to_the maximum design operating temperature of instrument supports and tubing. All tubing is currently being designed and installed using a maximum operating temperature criteria of 122 degrees F. Instrument supports and tubing could be exposed to temperatures in excess of 300 degrees F during certain accident scenarios (HELB or LOCA).

An engineering review and evaluation is currently being performed which addresses the above outlined concerns.

We will submit our next report on this issue no later than January 16, 1987.

I Very truly yours, ,

EA$m W. G. Counsil i i

JDS/mlh c - NRC Region IV (0 + 1 copy)

Director, Inspection & Enforcement (15 copies) '

U. S Nuclear Regulatory Commission l

Washington, D.C. 20555 r y ' A EN%1510% OF 1TXAS LTil1 TIES FLFCTRIC C0%IPAW c

8611070193 861029

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