L-98-077, Forwards Beaver Valley Unit 1,Cycle 13 Voltage-Based Repair Criteria 90-Day Rept, Which Supports Continued Implementation of 2.0 Volt Repair Criteria as Outlined in NRC GL 95-05
| ML20217D385 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 04/16/1998 |
| From: | Jain S DUQUESNE LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20217D389 | List: |
| References | |
| GL-95-05, GL-95-5, L-98-077, L-98-77, NUDOCS 9804240294 | |
| Download: ML20217D385 (2) | |
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Beav Valley Power Station Shippingport, PA 15077-0004 r e President Fax 7 64 8 Nuclear Power Division April 16,1998 L-98-077 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001
Subject:
Beaver Valley Power Station, Unit No.1 Docket No. 50-334, License No. DPR-66 Cycle 13 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 13 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 twelfth refueling outage at tube support plate intersections along with postulated steam line break leak rate and tube burst probability analysis results.
The permissible primary to secondary leak rate that would maintain offsite and control room doses within the applicable limits of 10 CFR 100 and GDC 19 was previously reported in Technical Specification Change No. 240 to be 11.75 gpm. A nonconservative fan flowrate assumption used in the control room radiation dose calculations that supported this amer.dment was identified which necessitated a reevaluation of the subject dose calculations. A complete extent of condition review of input assumptions and physical testing of the control room pressurization system identified several other necessary revisions to the dose calculations. Therefore, the dose calculations were revised and a new permissible primary to secondary leak rate of 8.0 gpm has been established. The 8.0 gpm leak rate is referenced in the attached report.
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Beaver Valley Power Station, Unit No.1 Cyci 13 Steam Generator Tube Inspection 90 Day Report Page 2 l
If you have any questions regarding the attached information, please contact Mr. J. Arias, Director, Safety and Licensing Department at (412) 393-5203.
Sincerely, l
Sushil C. Jain c:
Mr. D. S. Brinkman, Sr. Project Manager Mr. D. M. Kern, Sr. Resident Inspector Mr. H. J. Miller, NRC Region I Administrator 1
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