TXX-6338, Interim Deficiency Rept CP-86-83 Re Use of Separation Barrier Matl on Power Cables & Power Raceways W/O Derating Carrying Capacity Power.Thermal Barrier Matl in Process of Removal.Next Rept Will Be Submitted by 870605
| ML20204C668 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 03/20/1987 |
| From: | Counsil W, Keeley G TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| CP-86-83, TXX-6338, NUDOCS 8703250343 | |
| Download: ML20204C668 (2) | |
Text
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Log # TXX-6338 P9 File # 10110 C
908.3 C
Ref. # 10CFR50.55(e)
MIELECTRIC March 20, 1987 m,g c m w n m e ern a m U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 SEPARATION BARRIER MATERIAL ON POWER CABLES AND POWER RACEWAYS SDAR:
CP-86-83 (INTERIM REPORT)
Gentlemen:
On December 8, 1986, we verbally notified your Mr. Ian Barnes of a deficiency involving the use of Separation Barrier Material (SBM) on power cables and power raceways.
This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e). Our last interim report submitted was logged TXX-6281, dated February 13, 1987.
The discrepancy involves the installation of thermal SBM on power cables and/or power raceways without derating of the cables' power carrying capacity (ampacity).
We have completed our calculations and have concluded that, due to significant conservatism in cable sizing design, the subject cables and cables in raceways did not exceed their insulation temperature rating during start-up testing.
The thermal barrier material is in the process of being removed from the power cables and power raceways. However, in order to determine safety significance, we are continuing the process of determining if the cable sizing design was sufficiently conservative to allow for the necessary cable ampacity derating with SBM in place. Our evaluation will determine the impact of this issue on the safety of plant operations during its 40 year design life.
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TXX-6338 March 20, 1987 Page 2 of 2 We expect to submit our next report by June 5, 1987.
Very truly yours, W. G. Counsil By:
G. S. Keeley &
Manager,NuclearLidnsing WJH:1w c - Mr. E. H. Johnson - Region IV Mr. D. L. Kelley, RI - Region IV Mr. H. S. Phillips, RI - Region IV l