ML20108D916
| ML20108D916 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 05/03/1996 |
| From: | Noonan T DUQUESNE LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NPD1VPO:0472, NPD1VPO:472, NUDOCS 9605090121 | |
| Download: ML20108D916 (2) | |
Text
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)Q ' DUQU8Sne @ Company %'LV7eyPowerStation
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Shippingport. PA 15077 0004 3
THOMAS P. NOONAN M12) 393 7622 078." $r."l*f*"'
May 3,1996
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NPD1VPO:0472 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
Beaver Valley Power Station, Unit No.1 Docket No. 50-334, License No. DPR-66 i
Special Report in accordance with Appendix A, Beaver Valley Technical Specification 4.4.5.5.c, " Steam Generators", the following Special Report is submitted. This report is required to document, prior to resumption of plant operation, the results of steam generator tube inspections which fall into technical specification Category C-3.
Technical Specification 4.4.5.5.c:
The RC-E-1A steam generator was pre-designated as the generator required to be sampled during this inspection interval. Examination of the RC-E-1 A steam generator resulted in the designation as defective a total of seventy-nine (79) tubes. These defective tubes were identified using the Plus Point Probe examination of the hot leg top-of-tubesheet region. These tubes were removed from service through tube plugging.
Three additional tubes were removed from service in the 1 A steam generator, one due to Cold Leg Thinning and two due to Row 1 U-Bend indications.
The primary degradation mechanism affecting the Beaver Valley Power Station Unit 1 Steam Generators is Outside Diameter Stress Corrosion Cracking (ODSCC) at the hot leg top-of-tubesheet in the sludge pile regions and at tube support plate intersections.
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May 3,1996 NPD1VPO:0472 Page 2 Boric acid addition to the secondary water is continuing in an effort to reduce the propensity for ODSCC. Additionally, secondary water chemistry molar ratio control has been implemented to further mitigate the growth and propagation of ODSCC. Sludge lancing the secondary side top-of-tubesheets has been performed to remove accumulated sludge that contributes to the formation of the aggressive environment that can result in the initiation of ODSCC in this region.
Furthermore, secondary water chemistry control is optimized to keep corrosion product transport to the steam generators as low as possible to minimize the accumulation of new sludge during the operating cycle.
Sincerely, T.P.Noonan Division Vice President Nuclear Operations / Plant Manager GFZ/ntc 1
1
.'s May 3,1996 NPD1VPO:0472 Page 3 cc:
Mr. T. T. Martin, Regional Administrator United States Nuclear Regulatory Commission Region 1 475 Allendale F. cad King ofPrussia, PA 19406 Mr. D. S. Brinkman BVPS Licensing Project Manager United States Nuclear Regulatory Commission Washington, DC 20555 Mr. Larry Rossbach BVPS Senior Resident Inspector United States Nuclear Regulatory Commission Mr. J. A. Hultz Ohio Edison Company 76 S. Main Street Akron, OH 44308 Mr. Mark Gas Centerior Energy Corporation 6200 Oak Tree Boulevard j
Independence, OH 44101-4661 l
INPO Records Center 700 Galleria Parkway l
Atlanta, GA 30339-5957 Mr. Roben Maiers Dept.rtment of Environmental Resources P.O. Box 8469 State Office Building,13th Flocr Harrisburg, PA 17105-8469 Director, Safety Evaluation & Control Virginia Electric & Power Company P.O. Box 26666 l
One James River Plaza Richmond, VA 23261
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