ML20128L533
| ML20128L533 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 10/09/1996 |
| From: | Jain S DUQUESNE LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9610150111 | |
| Download: ML20128L533 (4) | |
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Duquesne U@ Company g y rs' *a Shippingport, PA 15077 0004 i
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SEN am October 9' 1996 r.x N E E 0ll:::*: 1.
U. S. Nuclear Regulatory Commission Attention: Document Control Desk i
Washington, DC 20555-0001
Subject:
Beaver Valley Power Station, Unit No. 2 Docket No. 50-412, License No. NPF-73 Special Report In accordance with Appendix A, Beaver Valley Technical Specification 4.4.5.5.a,
" Steam Generators," the following Special Report is submitted. This report is required to document the results of the Inservice Inspection of steam generator tubes, performed during the Sixth Refueling Outage.
On September 24,1996, the Inservice Inspection of the tubing in steam generators 2RCS-SG21A,2RCS-SG21B, and 2RCS-SG21C was completed. The number of tubes inspected and a breakdown of tubes removed from service for each generator is documented in Attachment 1.
One hundred percent (100%) of all inservice tubes in steam generators 2RCS-SG21A, 2RCS-SG21B, and 2RCS-SG21C were examined full length with bobbin coil probes. The Zetec 3-Coil Rotating Pancake Coil Probe (RPC) was used on indications that could not be resolved through standard bobbin coil testing. In addition, the Zetec Plus Point Probe was used to examine 100% of the hot leg top-of-tubesheet region in each steam generator. Crack-like indications identified in the hot leg top-of-tubesheet region were removed from service. Circumferentialindications were stabilized.
Examination of the steam generator preselected to meet the Technical Specification required sample, 2RCS-SG21A, resulted in a total of twenty (20) tubes being removed from service.
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Beaver Valley Power Station, Unit No. 2 Special Report Page 2 Attachment I lists the applicable tubes for each steam generator and the location and the extent of degradation in accordance with Technical Specification 4.4.5.5.a.
Sincerely, Sushil C. Jain
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Besver Valley Power Station, Unit No. 2 Special Report Page 3 c:
Mr. H. J. Miller, Regional Administrator
' United States Nuclear Regulatory Commission 4
Region 1 475 Allendale Road King of Prussia, PA 19406 Mr. D. S. Brinkman BVPS Licensing Project Manager United States Nuclear Regulatory Commission Washington, DC 20555 Mr. D. M. Kern 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 Burns Centerior Energy Corporation 6200 Oak Tree Boulevard Independence, OH 44101-4661 INPO Records Center 700 Galleria Parkway Atlanta, GA 30339-5957 Mr. Robert Maiers Department of Environmental Resources P.O. Box 8469 State Office Building,13th Floor Harrisburg, PA 17105-8469 Director, Safety Evaluation & Control Virginia Electric & Power Company P.O. Box 26666 One James River Plaza Richmond, VA 23261
Beaver Valley Pswer Station, Unit No. 2 Docket No. 50-412, License No. NPF-73 Special Report ATTACHMENT 1 2RCS-SG21A 2RCS-SG21B 2RCS-SG21C Total number of tubes in generator 3376 3376 3376 Number of tubes previously removed from service 64 56 64 Number of tubes examined full length (with bobbin 3312 3320 3312 coil probes)
Number of new tubes removed from service this 20 19 24 outage Pitting at Top-of-Tubesheet 8
Greater than 40% Tech Spec limit 0
0 0
Confirmed DSI's @ Tube Support Plates 3
1 Top of Tubesheet Indications (Circumferential/
17 ($ 9 17 (8/9) 10 (4/6)
Axial)
Free Span Indication (Between Support Plates) 1 5
Large Permeability Signal (Possibly masking 1
indication)
Total number of tubes currently removed from 84 75 88 service (post sixth refueling outage)
Percentage of tubes currently plugged 2.49%
2.22 %
2.61 %
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