ML20247K438
| ML20247K438 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 05/26/1989 |
| From: | William Cahill TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| CP-88-25, TXX-89269, NUDOCS 8906010299 | |
| Download: ML20247K438 (2) | |
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Log '# TXX-89269 File # 10110 l
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Ref. # 10CFR50.55(e) illELECTRIC William J. Cahill. Jr.
i Enecutive Vice President '
l U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C.
20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 AUXILIARY FEEDWATER PUMP TURBINE CONTROL PANEL 1
SDAR:
CP-88-25 (SUPPLEMENTAL REPORT)
Gentlemen:
On January 29, 1988, TU Electric notified the NRC via report logged TXX-88170, of a deficiency in the design of the Auxiliary Feedwater (AFW) Pump Turbine control panel which could impair the safety function of the Auxiliary feedwater System. The last report was logged TXX-89148, dated March 14, 1989.
A written report was due on May 24, 1989.. TU Electric verbally requested and l
received an extension from your Mr. S. D. Bitter until May 31, 1989.
The purpose of this report is to revise the corrective action for this deficiency.
In TXX-88170 dated January 29, 1988, TU Electric stated that the AFW Pump Turbine control panel would be fully qualified to meet the requirements for its design basis safety function.
Subsequently, TXX-88514 dated June 30, 1988, revised the corrective action and indicated the panel would be automatically isolated during all automatic starts of the pump.
In lieu of fully qualifying the panel or automatically isolating the panel, as described above, the 480V power supply cable to the motor operator of the trip and throttle valve,1-HV-2452, has been disconnected + tam the starter terminals and spared in place. The trip solenoid control circuit has been rewired to completely bypass the turbine control circuit such that any postulated fault at the control panel would not cause the trip solenoid to be energized. The existing -Safety Injection Signal that isolates the Class IE power supply to the control panel has not been altered.
8906010299 890526 PDR ADOCK 05000445 S
PNU 1
1 I O 400 North Olive Street LB 81 Dallas, Texas 75201 L_ ___
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- TXX-89269 May: 26,11989
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Page 2.of 2 The corrective action for.. Unit 1 is complete. The corrective action schedule
- for Unit 2 remains unchanged.
Sincere 1y,
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William J. Ca 111', Jr.
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- VPC/ddm c - Mr.
R..D. Martin, Region IV-m Residant Inspectors, CPSES (3)
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