TXX-6220, Final Deficiency Rept CP-86-70 Re Elevated Temp Effects on Instrument Supports & Tubing.Initially Reported on 861002. Installations & Mods Will Be Implemented as Required to Alleviate Unacceptable Conditions
| ML20212J708 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 01/16/1987 |
| 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-6220, NUDOCS 8701280276 | |
| Download: ML20212J708 (2) | |
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..T Log #TXX-6220 File # 10010 903.11 TEXAS UTILITIES GENERATING COMPANY DEVWAY TOWWht e 4AB NORT,0 OtJVE WFRENT. B.B. Si e B,AI.8.AA. TEXA4 70ml
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EMIT #.UI!b January 16, 1987
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A' Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS 50-445 AND 50-446 ELEVATED TENPERATURE EFFECTS ON INSTRUMENT SUPPORTS AND TUBING SDAR: CP-86-70 (FINAL 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. Our latest report was logged TXX-6067 and was submitted October 29, 1986. We are reporting this issue under the provisions of 10CFR50.55(e) and the required information follows.
Description 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).
Safety Imolications In the event the deficiency had remained undetected, the integrity of the instrumentation tubing could not be assured during accident conditions.
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' TXX-6220 January 16, 1987 Page 2 of 2 Corrective Action Upon completion of the evaluation of existing installations, modifications will be implemented as required to alleviate unacceptable conditions. The status of modifications will be reported under 10CFR50.55(e) via SDAR CP 19.
Very truly yours, s/
'lI r2 vMtdo W. G. Counsil JDS/est c - NRC Region IV (0 + 1 copy)
Director, Inspection and Enforcement (15 copies)
U. S. Nuclear Regulatory Commission Washington, D. C.
20555
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