ML20084S745
| ML20084S745 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| 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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&ngGy, Directorate of Office of Nuclear Reactor Regulation U. S. HUCLEAR REGULATORY COMMISSION j
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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 N'
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c 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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k 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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