ML20245J977
| ML20245J977 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak |
| Issue date: | 08/10/1989 |
| From: | William Cahill TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| CP-89-009, CP-89-9, TXX-89549, NUDOCS 8908180246 | |
| Download: ML20245J977 (2) | |
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Log # TXX-89549 n
File # 10110 903.9 Ref. # 1 CFR50.55(e) 7UELECTRIC E,"I,,",hf/I,',$jf; August 10, 1989 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C.
20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NO. 50-445 DEFICIENT MODIFICATION TO PIPE WHIP RESTRAINT SDAR:
CP-89-009 (FINAL REPORT)
Gentlemen:
On May 8,1989 TU Electric notified the NRC by report logged TXX-89252 of a deficiency involving an improper modification of a single pipe whip restraint.
Af ter further evaluation, it has beers concluded this deficiency is reportable under the provisions of 10CFR50.55(e). The required information follows.
DESCRIPTION A Design Change Authorization (DCA) authorized removal of lugs from certain Chemical Volume and Control System (CVCS) charging system piping. This piping is used for the normal charging to the Reactor Coolant System (RCS) and is also utilized to inject boron during a reactor safe shutdown.
The removed lugs associated with this piping are required to ensure that the pipe will not slip through its pipe whip restraint during a postulated high energy line break.
Since this restraint is located in a room (outside of containment) which contains piping related to both the normal and alternate boration paths, both boration paths could potentially be lost as a result of unrestrained pipe whip.
Due to the unique configuration and location of this pipe whip restraint, it was incorrectly assumed that the removed lugs were part of an abandoned pipe support.
Hence, this deficiency is considered to be an isolated case.
1 SAFETY SIGNIFICANCE Loss of the normal and alternate boration paths due to an unrestrained pipe whip could adversely affect the ability to safely shut down the plant.
Therefore, this deficiency is reportable under the provisions of 10CFR50.55(e).
1 E:90B180246 090810 N
PDR ADOCK 05000445 S
PNU t t 400 North Olive Street LB 81 Dallas, Texas 75201
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CORRECTIVE ACTION-a.
The lugs are being replaced on the affected Unit I system p hing. This. action
--will be complete prior to Unit I fuel load, Sincerely, William J. Cahill. Jr.
SEC/smp c - Mr. R; D. Martin, Region IV Resident Inspectors, CPSES (3)
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