ML050320038
| ML050320038 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 01/26/2005 |
| From: | Pearce L FirstEnergy Nuclear Operating Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| GL-95-005, L-05-012 | |
| Download: ML050320038 (2) | |
Text
--FENOC Beaver Valley PowverStation PO. Box4 FirstEnergy Nuclear Operating Company Shippingport, PA 15077-0004 L William Pearce 724-682-5234 Vice President Fax: 724-643-8069 January 26, 2005 L-05-012 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001
Subject:
Beaver Valley Power Station, Unit No. I Docket No. 50-334, License No. DPR-66 Cycle 17 Steam Generator Tube Inspection 90 Day Report Reference 1:
NRC Generic Letter 95-05, "Voltage-Based Repair Criteria for the Repair of Westinghouse Steam Generator Tubes Affected by Outside Diameter Stress Corrosion Cracking," August 3, 1995.
Enclosed is a copy of the "Beaver Valley Unit 1 Cycle 17 Voltage-Based Repair Criteria 90-Day Report," which supports continued implementation of the 2.0 volt repair criteria as outlined in Reference 1. This report provides a summary of the steam generator inspections performed during the sixteenth refueling outage at tube support plate intersections along with postulated steam line break leak rate and tube burst probability analysis results.
In accordance with Beaver Valley Power Station (BVPS) Unit No. I Technical Specification 4.4.5.5.e which requires that a Steam Generator Special Report be submitted within 90 days following return of the steam generators to service (Mode 4),
Appendix A of the enclosed report provides the aggregate calculated steam line break leakage from the application of tube support plate alternate repair criteria and W*
methodology. Appendix A also supplies the identified indications performed as part of the W* inspections.
In accordance with Section 3.1.7 of NEI 97-06, Appendix B of the enclosed report provides a synopsis of the BVPS Unit No. 1. sixteenth refueling (IR16) condition monitoring report due to the steam generator inspection being categorized as C-3.
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- Beaver Valley Power Station, Unit No. I Cycle 17 Steam Generator Tube Inspection 90 Day Report L-05-012 Page 2 There are no new regulatory commitments contained in this submittal. If there are any questions concerning this matter, please contact Mr. Larry R. Freeland, Manager, Regulatory Compliance at 724-682-4284.
Sincerely, William Pearce Attachments c:
Mr. T. G. Colburn, NRR Senior Project Manager Mr. P. C. Cataldo, NRC Sr. Resident Inspector Mr. S. J. Collins, NRC Region I Administrator Mr. D. A. Allard, Director BRP/DEP Mr. L. E. Ryan (BRP/DEP)