ML18139A842

Suppls 800424 Response to IE Bulletin 79-13,Revision 2,re Cracking in Feedwater Sys Piping.No Reportable Indications Found During Listed Insps

ML18139A842
Person / Time
Site:	Surry
Issue date:	11/07/1980
From:	Sylvia B VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
901, IEB-79-13, IEB-79-13-R2, NUDOCS 8011210352
Download: ML18139A842 (2)

Text

RICllMOND,VIHOIN.lA 23261 VIRGINIA. ELECTRIC AND POWER COMPANY

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.I November 7 3 1980 Mr. James P. O'Reilly, Director Serial No. 901 Office of Inspection and Enforcement NO/FHT Region II Docket No. 50-280 U.S. Nuclear Regulatory Commission License No. DPR-32 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303

Dear Mr. O'Reilly:

IE BULLETIN 79-13 REVISION 2 SURRY POWER STATION UNIT 1 FINAL REPORT In response to the subject bulletin, "Cracking in Feedwater System Piping", we are forwarding the following inspection results. As noted in our previous letter dated April 24, 1980, Serial No. 369, th_e feedwater pipe-to-penetration seal fillet welds and the auxiliary feedwater to main feedwater pipe connec-tions were to be inspected during an upcoming refueling outage. In addition, we committed to inspect the steam generator nozzle,-to-reducer and reducer-to-feedwater line welds on the new replacement 14" by 16" reducers installed last year after cracking was identified by inspections required by the bulletin.

These inspections have recently been completed* on Surry Unit 1:

1. Feedwater Penetration Fillet Welds A magnetic particle inspection has been performed on all feedwater pipe-to-penetration seal fillet welds. There were no reportable indications.

2. Auxiliary Feedwater/Main Feedwater Tie-in A volumetric (radiographic) inspection was performed on the main feedwater pipe for a distance of 14 inches (one pipe diameter) down-stream of the junction. No reportable indications were found.

3. Steam Generator Nozzle to Feedwater Pipe Reducers

• A volumetric (radiographic) inspection was performed on the nozzle-to-reducer and reducer-to-feedwater pipe welds on all three reducers.

The* inspection covered the area two wall thicknesses (2T) on each side of each weld. There were no reportable indications.

V!ROJNU El,ECTIIJC AND Pow1m COMPANY TO

• Mr. James P. b'Reilly, Director This concludes the 'responses required to comply with the requirements of IE Bulletin 79-13 Revision 2. If you require additional information, please contact this office.

Very truly yours,

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B. R. -Sylvia Manager - Nuclear Operations and Maintenance smv:SE2 cc: Director, Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation Attention: Mr. Steven A Varga, Chief Operating Reactors Branch 1 Division of Licensing U. S. Nuclear Regulatory Commission -,-

Washington, D. C. 20555