ML19327A037

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Safety Evaluation Re RHR Pump Suction Line Insp.Crack Is Not Generic.Weld Repair Was Effective
ML19327A037
Person / Time
Site: Brunswick  
Issue date: 07/23/1980
From:
Office of Nuclear Reactor Regulation
To:
Shared Package
ML19327A028 List:
References
NUDOCS 8008010090
Download: ML19327A037 (1)


Text

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7LJ BRUNSWICK UNIT 2 RHR PUMP SUCTION LINE INSPECTION SAFETY EVALUATION REPORT ENGINEERING BRANCH DIVISION OF OPERATING REACTORS

1.0 INTRODUCTION

Carolina Power and Light Company reported in Licensee Event Report 2-76-161, dated January 26, 1977, that a crack was discovered in the Residual Heat Removal (RHR) pump suction line. A follow-up inspection on the RHR suction lines was performed in January 1980 to determine if new cracks had occurred since 1977 and to obtain infomation on the amplitude of vibration of the lines.

2.0 EVALUATION The enclosed Technical Evaluation Report was prepared for us by our contractor, Franklin Research Center, as part of NRC Contract No. NRC-03-79-ll8.

3.0 CONCLUSION

We have reviewed the enclosed contractor's Technical Evaluation Report, and agree with their findings that this crack occurrence is not due to a generic design defect and that the weld repair on the cracked suction line was effective in preventing further crack initiation.

8008010@D