ML20246G991

Final Deficiency Rept CP-88-42 Re Cold Spring in Component Cooling Water Piping Involving Flange Misalignment.Initially Reported on 890406.Condition Adverse to Safety of Operations Determined Not to Exist & Not Created by Alignment

ML20246G991
Person / Time
Site:	Comanche Peak
Issue date:	07/10/1989
From:	William Cahill TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
CP-88-42, TXX-89455, NUDOCS 8907140295
Download: ML20246G991 (2)

Text

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M Log # TXX-89455

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filELECTRIC WMiam J. Cahill, Jr.

Executive Vice President U. S. Nuclear Regulatory Commission Attn:. Document Control Desk Washington, D. C. 20555

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NO. 50-445 C0tD SPRING IN COMPONENT COOLING WATER PIPING SDAR: CP-88-42 (FINAL REPORT)

Gentlemen:

On December 7, 1988, TU Electric notified the NRC of a deficiency discovered during maintenance activities on valve 1HV-4514 in the Unit 1 Component Cooling Water (CCW) system involving a flange misalignment. The last report on this issue was logged TXX-89182 dated April 6, 1989. After further review of this deficiency it was concluded that the criteria for deportability have not been met, and this deficiency is not reportable pursuant to 10CFR50.55(e),

i During maintenance activities associated with removal and reinsta11ation of  !

valve 1HV-4514 in the Unit 1 CCW system, a hydraulic jack was utilized to- ,

correct a pipe misalignment that was observed during the valve removal. The use of the jack was not authorized by engineering, as was reauired by site procedures.

Evaluation of this issue included a review of administrative procedures controlling the use of hydraulic jacks for pipe alignment purposes, calculations of pipe and hanger stresses generated during alignment of the subject piping, and review of engineering / construction activities associated with the affected piping to identify the probable cause of residual forces that resulted in the pipe displacement noticed during the valve removal. The piping stress and support loads were shown to be acceptable.

Based on this evaluation of the pipe and hanger stresses generated during the i l

pipe realignment, it was determined that a condition adverse to the safety of plant operations did not exist prior to the discovery of the misalignment and consequently was not created during the subsequent realignment. This is the basis for concluding the issue does not meet the criteria for deportability and this deficiency is not reportable pursuant to 10CFR50.55(e).

8907140295 890710 s PDR ADOCK 05000445 gU>1

' l S PDC i f d 400 North Olive Street LB 81 Dallas, Texas 75201

TXX-89455 July 10, 1989 Page 2 of 2 This is the final report on this deficiency. Records supporting the evaluations and conclusions are available for review.

Sincerely,

(

I Cn William J. Cahill, Jr.

MCP/vid c - Mr. R. D. Martin, Region IV Resident Inspectors, CPSES (3) l

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