TXX-6230, Final Deficiency Rept CP-86-16 Re Detrimental Effects of Low Melting Point Metals on Stainless Steel Instrument Tubing During Fire.Initially Reported on 860321.Mods Will Be Implemented as Required
| ML20212J558 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 01/21/1987 |
| From: | Counsil W TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| To: | Johnson E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| References | |
| CP-86-16, TXX-6230, NUDOCS 8701280232 | |
| Download: ML20212J558 (2) | |
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Log # TXX-6230 File # 10110 903.11 TEXAS UTILITIES GENERATING COMPANY SKYWAY TOWER. 4e0 NORTH OLIVE STRE8fr.1.B. 81. DALLAS, TEXA8 76305
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[L Mr. Eric H. Johnson, Director Division of Reactor Safety and Projects 1
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 FIRE EFFECTS ON INSTRUMENT TUBING SDAR: CP-86-16 (FINAL REPORT)
Dear Mr. Johnson:
On March 21, 1986, we verbally notified your Mr. R. Hall of a deficiency involving the detrimental effects of low melting point metals (zinc) on stainless steel instrument tubing during a fire. Our latest report logged TXX-6034 was submitted October 20, 1986. We are reporting this issue under the provisions of 10CFR50.55(e) and the required information follows.
Description This deficiency involves the possible damaging effects of low melting point metals on stainless steel instrument tubing associated with instruments required for fire safe shutdown (but not alternate shutdown). The significance of stainless tubing in direct contact with galvanized material (zinc) such as Unistrut supports and clamps during a fire has been evaluated by engineering, primarily focusing on the possibility of safey related redundant counterpart instrument tubing designed to route through the same fire zone.
Safety Imolications In the event this deficiency had remained undetected, the integrity of the instrumentation tubing could not be assured during a post-fire accident condition.
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- se-TXX-6230 January 21, 1987 Page Two of Two Corrective Action Upon completion of the identification of existing installations, modifications will be implemented as required to alleviate all unacceptable conditions. The status of modifications will be reported under 10CFR50.55(e) via SDAR CP 19.
Very truly yours,,
W. G. Counsil JDS/est
- NRC Region IV (0 + 1 copy)
Director, Inspection & Enforcement (15 copies)
U. S. Nuclear Regulatory Commission Washington, D.C.
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