ML20084S745

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AO 50-265/75-19:on 750523,break Discovered in Clean Up Sys Pipe Weld.Caused by Vibration Stressed Weld.Weld Plug Installed.Line Will Be Replaced in Future
ML20084S745
Person / Time
Site: Quad Cities Constellation icon.png
Issue date: 05/30/1975
From: Kalivianakis N
COMMONWEALTH EDISON CO.
To:
Office of Nuclear Reactor Regulation
Shared Package
ML20084S748 List:
References
AO-50-265-75-19, NJK-75-299, NUDOCS 8306170213
Download: ML20084S745 (2)


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Directorate of Office of Nuclear Reactor Regulation l U. S. HUCLEAR REGULATORY COMMISSION j Washington, D. C. 20555 1 l

REFERENCE:

Quad-Cities Nuclear Power Station Docket No. 50-265, DPR-30, Unit 2 Appendix A, Sections 1.0.A.5, 3.7.A.2, 6.6.B.l.a '

Enclosed please find Abnormal Occurrence Report No. A0-50-265/75-19 for Quad-Citics Nuclear Power Station. This occurrence was previously reported to Region li t , Directorate of Regulatory Operations by telephone on May 24, 1975 and to you and P,cgion li t , Directorate of Regulatory Operations by telecopy on May 24, 1975 This report is submitted to you in accordance with the requirements of Tech-nical Specificatien 6.6.8.1.a.

Very truly yours, COMMONWEALTH EDIS0N COMPANY QUAD-C IT I ES NUCLEAR P0'..'ER STAT ION l c N' 4W N. J. Kalivianakis C Station Superintendent NJK:TLS/dkp cc: Region 111, Directorate of Regulatory Operations J. S. Abel .

8306170213 750530 PDR ADOCK 05000265 PDR S

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REPORT NUMBER: A0-50-265/75-19 .

REPORT DATE: May 30, 1975 0CCURRENCE DATE: May 23, 1975 -

FACILITY: Quad Cities Nuclear Power Station Cordova, Illinois 62142

'lDENTIFICATION OF OCCURRENCE:

Clean up system pipe weld break Unit Two.

CONDITIONS PRIOR TO OCCURREdCE:

Run mode at 712 MWe.

DESCRIPTION OF OCCURRENCE:

On May 22, 1975 the reactor building vent system air activity increased significantly.

This led the rad-chem department'to suspect a system leak somewhere within the reactor building. On May 23, at 8:30PM, an operator making rounds in search of a steam leak found steam issuing from a pipe in the clean up heat exchange room. At 9:30PM, the leak was isolated and identified as a 3/4" test connection (PX) weld from the 3/4" line to the weld-0-Ict on the 4" line (2-1205-4"A) between the 2-1201-30 and 2-1201-82 valves.

DESIGNATION OF APPARENT CAUSE OF OCCURRENCE:

Equipment Failure: A vibration stressed weld is designated the apparent cause of

'the occurrence. The. weld failure occurred as.a crack in the heat effected zone.

ANALYSIS OF OCCURRENCE:

Since the leak was isolated upon i ts discovery, a minimum amount of radioactive contamination ~was released from the clean up heat exchange room. The-reactor-building vent stack technical specification limits were not exceeded. There-fore the health and safety of the public were not affected by this occurrence.

CORRECTIVE ACTION:

The test (PX) connection was removed to the affected weld at the weld-o-let and a-weld plug was installed. - The line will be replaced in the future as necessary to

  • facilitate leak rate testing. .

FAILURE DATA:

ITest connection (PX) line weld failures have not occurred previously in this system.

Therefore, there are no safety implications from cumulative experience related to this occdrrence. .

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