L-05-083, R11 Steam Generator Tube Plug Special Report
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Letter Sequence Request | |
|---|---|
TAC:MC8770, (Approved, Closed) | |
Administration | |
MONTHYEARL-05-076, R11 Steam Generator C-3 Report2005-04-19019 April 2005
[Table View]R11 Steam Generator C-3 Report Project stage: Request L-05-083, R11 Steam Generator Tube Plug Special Report2005-04-26026 April 2005 R11 Steam Generator Tube Plug Special Report Project stage: Request L-05-114, Eleventh Refueling Steam Generator Condition Monitoring Report2005-07-0505 July 2005 Eleventh Refueling Steam Generator Condition Monitoring Report Project stage: Request L-05-161, Year 2004/2005 Steam Generator Examination Reports2005-10-14014 October 2005 Year 2004/2005 Steam Generator Examination Reports Project stage: Request ML0535400052005-12-21021 December 2005 (BVPS-1 and 2) - Request for Additional Information (RAI) - 2004 and 2005 Steam Generator (SG) Tube Inspections (TAC Nos. MC8770 and MC8771) Project stage: RAI L-06-008, Response to Request for Additional Information on 2004 and 2005 Steam Generator Tube Inspections2006-04-0707 April 2006 Response to Request for Additional Information on 2004 and 2005 Steam Generator Tube Inspections Project stage: Response to RAI ML0615105112006-06-14014 June 2006 (BVPS 1 and 2) - Review of the 2004 and 2005 Steam Generator (SG) Tube Inspections Reports (TAC Nos. MC8770 and MC8771) Project stage: Approval 2005-04-26 |
| ML051220112 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 04/26/2005 |
| From: | Pearce L FirstEnergy Nuclear Operating Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| L-05-083 | |
| Download: ML051220112 (3) | |
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FENOC __1 Beaver Valley PowerStation PO. Box 4 FirstEnergy Nuclear Operating Company Shippingport, PA 15077-0004 L. William Pearce 724-682-5234 Vice President Fax: 724-643-8069 April 26, 2005 L-05-083 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001
Subject:
Beaver Valley Power Station, Unit No. 2 Docket No. 50-412, License No. NPF-73 2R11 Steam Generator Tube Plug Special Report In accordance with Beaver Valley Power Station (BVPS) Unit No. 2 Technical Specification 4.4.5.5.a which requires that a Steam Generator Special Report be submitted within 15 days of completion of steam generator inspections, Attachment I lists the number of tubes removed from service (plugged) from each steam generator during the 2R1 I refueling outage. No steam generator tubes were repaired (sleeved) during 2R11.
The following examinations were performed during 2R1 1:
100% full length 0.720" bobbin coil examination of all in-service tubes in Rows 5 through Row 46 100% 0.720" bobbin coil examination of all straight tube sections in Rows I through Row 4 100% 0.700" bobbin coil examination in the U-bend region of Rows 3 and 4 100% +Point inspection of all tube support plate (TSP) distorted signal indications (DSI) 100% +Point inspection of all TSP mix residual signals Ž 2 volts 100% +Point inspection of dented hot leg TSP intersections 2 5 volts 100% +Point inspection of > 2 volts but < 5 volts dents at the 1st, 2nd, 3rd, and 4th hot leg TSPs 100% +Point inspection of TSP mix residuals < 55 degrees phase and 2 1.25 volts 100% +Point inspection in each steam generator (SG) from 6" above to 3" below the hot leg top-of-tubesheet (TTS) 100% +Point inspection of the Row 1 and 2 small radius U-bend region in each SG 100% +Point inspection of freespan dings > 5 volts 100% +Point inspection of freespan signals not resolved as Manufacturing Burnish Marks 100% +Point inspection of dents at anti-vibration bar (AVB) intersections nt6
- Beaver Valley Power Station, Unit No. 2 2R1 1 Steam Generator Tube Plug Special Report L-05-083 Page 2 100% +Point inspection of bulges within the hot and cold leg tubesheet above the neutral axis 20% +Point inspection of TSP mix residual signals > 1.5 volts but < 2 volts 20% +Point inspection of the Rows 3 through 8 U-bend region in each SG 20% +Point inspection of bobbin coil AVB wear indications 20% +Point inspection of > 2 volts but < 5 volts dents at the 5th hot leg TSP The complete and detailed results of the 2R1 1 steam generator tube inspections will be submitted within the next 12 months in accordance with BVPS No. 2 Technical Specification 4.4.5.5.b.
No new commitments are 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 Attachment 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
el: . ..
ATTACHMENT 1 TO L-05-083 2RCS- 2RCS- 2RCS-SG21A SG21B SG21C Number of tubes removed from service prior to 2R11 137 126 122 Number of tubes removed from service during 2R11 14 34 7 Axial Indications Above the Hot Leg Tubesheet 1 5 1 Circumferential Indications Above the Hot Leg Tubesheet 4 4 Circumferential Indications Within the Hot Leg Tubesheet 9 22 5 Volumetric Indication Within Hot Leg Tubesheet 1 Confirmed Tube Support Plate Distorted Signals 2 Permeability Variation 1 Number o tubes removed from service after 2R11 151 160 129