TXX-6723, Interim Deficiency Rept CP-87-29 Re Component Cooling Water Isolation Following Reactor Coolant Pump Thermal Barrier HX Rupture.Initially Reported on 870629.Evaluation of Effects Continuing.Next Rept Will Be Submitted by 871120
| ML20234B646 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 09/14/1987 |
| From: | Counsil W TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| CP-87-29, TXX-6723, NUDOCS 8709210025 | |
| Download: ML20234B646 (1) | |
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Log # TXX-6723 i
j File # 10110
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909.2 Ref: 10CFR50.55(e) 7UELECTRIC wmiam c. counsa September 14, 1987 Executive Vice Pres &nt j
U. S. Nuclear Regulatory Commission Attn:
Document Control Desk Washington, D.C. 20555 1
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET N05. 50-445 AND 50-446
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COMPONENT COOLING WATER (CCW) ISOLATION FOLLOWING REACTOR COOLANT PUMP (RCP) THERMAL BARRIER RUPTURE SDAR:
CP-87-29 (INTERIM REPORT) 1 Gentlemen:
j On June 29, 1987 we verbally notified your Mr. Shannon Phillips of a deficiency involving instrumentation and controls utilized for isolation of Component Cooling Water (CCW) to the Reactor Coolant Pump (RCP) thermal barrier heat exchanger.
This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e).
Our latest interim report logged was TXX-6608, dated July 29, 1987.
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Our evaluatir;n of the effects of this condition is continuing.
The next report on inis issue will be submitted no later than November 20, 1987.
l Very truly yours, NI W. G. Counsil CBC/mlh c - Mr. R. D. Martin, Region IV Resident inspectors, CPSES (3) 8709010025 870914 PDR ADOCK 05000445 S
PDR 91 400 North Olise Street LB 81 Dallas. Texas 75201
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