ML121290532: Difference between revisions
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{{#Wiki_filter:UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 May 16, 2012 Mr. Paul Site Vice President FirstEnergy Nuclear Operating Company Beaver Valley Power Station Mail Stop A-BV-SEB1 P.O. Box 4, Route 168 Shippingport, PA 15077 SUB..BEAVER VALLEY POWER STATION, UNIT NO.2 -REVIEW OF STEAM GENERATOR TUBE INSPECTION REPORT FOR SPRING 2011 REFUELING OUTAGE (TAC NOS. ME7382 AND ME7383) | {{#Wiki_filter:UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 May 16, 2012 Mr. Paul A. Harden Site Vice President FirstEnergy Nuclear Operating Company Beaver Valley Power Station Mail Stop A-BV-SEB1 P.O. Box 4, Route 168 Shippingport, PA 15077 SUB..BEAVER VALLEY POWER STATION, UNIT NO.2 -REVIEW OF STEAM GENERATOR TUBE INSPECTION REPORT FOR SPRING 2011 REFUELING OUTAGE (TAC NOS. ME7382 AND ME7383) Dear Mr. Harden: By letters dated June 9, 2011 (Agencywide Documents Access and Management System (ADAMS) Accession Number ML 111600250), and September 20,2011 (ADAMS Accession Number ML 112630318), FirstEnergy Nuclear Operating Company (the licensee) submitted information summarizing the results of steam generator (SG) tube inspections at Beaver Valley Power Station (BVPS), Unit No.2. These inspections were performed during the spring 2011 refueling outage. These reports were submitted pursuant to BVPS, Unit No.2, Technical Specifications (TSs) 5.6.6.2.4, and 5.6.6.2.1, respectively. In addition to these reports, the U.S. Nuclear Regulatory Commission (NRC) staff summarized a conference call with the licensee about the 2011 SG tube inspections in a letter dated June 15, 2011 (ADAMS Accession Number ML 111580515). The NRC staff has completed its review of the submittals pertaining to the BVPS, Unit No.2, SG inspections, and the associated review summary is enclosed. The NRC staff finds that the licensee has provided the information required by the TSs. In addition, the staff did not identify any technical issues that warrant follow-up action at this time. Based on these considerations, the subject TACs are being closed. Please contact me at 301-415-2833, if you have any questions. _ Peter Bamford, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-412 Enclosure: As stated cc w/encl: Distribution via Listserv REVIEW OF THE SPRING 2011 STEAM GENERATOR TUBE INSPECTION REPORT FIRST ENERGY NUCLEAR OPERATING COMPANY BEAVER VALLEY POWER STATION, UNIT 2 DOCKET NO. 50-412 By letters dated June 9, 2011 (Agencywide Documents Access and Management System (ADAMS) Accession Number ML 111600250), and September 20,2011 (ADAMS Accession Number ML 112630318), FirstEnergy Nuclear Operating Company (the licensee) submitted information summarizing the results of the 2011 steam generator (SG) tube inspections at Beaver Valley Power Station (BVPS), Unit NO.2. These inspections were performed during the spring 2011 refueling outage. These reports were submitted pursuant to BVPS, Unit No.2, Technical Specifications (TSs) 5.6.6.2.4, and 5.6.6.2.1, respectively. In addition to these reports, the U.S. Nuclear Regulatory Commission (NRC) staff summarized a conference call with the licensee about these 2011 SG tube inspections in a letter dated June 15, 2011 (ADAMS Accession Number ML 111580515). BVPS, Unit 2, is a 3-loop plant with Westinghouse Model51M SGs. Each SG contains 3376 mill-annealed, Alloy 600 tubes with a nominal outside diameter of 0.875 inches, and a nominal wall thickness of 0.050 inches. The tubes are supported by a number of carbon steel tube support plates and Alloy 600 anti-vibration bars. The tubes were roll expanded at both ends for the full depth of the tubesheet. The entire length of tube within the tubesheet was shot-peened on both the hot-leg and cold-leg side of the SG, prior to operation. In addition, the U-bend region of the small radius tubes were in-situ stress relieved prior to operation. The licensee provided the scope, extent, methods, and results of their steam generator tube inspections in the documents referenced above. In addition, the licensee described corrective actions (Le., tube plugging or repair) taken in response to the inspection findings. Based on the NRC staffs review of the information submitted by the licensee, the staff has the following observation: A tube in Row 29, Column 12, of SG "C" had sporadic permeability variations between the 4th cold-leg and 7th hot-leg tube support plates, which could not be adequately compensated for by magnetically biased bobbin or +PtŽ probes. As a result, the licensee in-situ pressure tested the entire tube. The tube passed the in-situ pressure test and was then stabilized and plugged. Based on a review of the information provided, the NRC staff concludes that the licensee provided the information required by the BVPS, Unit No.2, TSs. In addition, the staff concludes that there are no technical issues that warrant follow-up action at this time, since the inspections appear to be consistent with the objective of detecting potential tube degradation and the inspection results appear to be consistent with industry operating experience at similarly designed and operated units. Enclosure May 16, 2012 Mr. Paul A. Harden Site Vice President FirstEnergy Nuclear Operating Company Beaver Valley Power Station Mail Stop A-BV-SEB1 P.O. Box 4, Route 168 Shippingport, PA 15077 BEAVER VALLEY POWER STATION, UNIT NO.2 -REVIEW OF STEAM GENERATOR TUBE INSPECTION REPORT FOR SPRING 2011 REFUELING OUTAGE (TAC NOS. ME7382 AND ME7383) Dear Mr. Harden: By letters dated June 9,2011 (Agencywide Documents Access and Management System (ADAMS) Accession Number ML 111600250), and September 20,2011 (ADAMS Accession Number ML 112630318), FirstEnergy Nuclear Operating Company (the licensee) submitted information summarizing the results of steam generator (SG) tube inspections at Beaver Valley Power Station (BVPS), Unit NO.2. These inspections were performed during the spring 2011 refueling outage. These reports were submitted pursuant to BVPS, Unit No.2, Technical Specifications (TSs) 5.6.6.2.4, and 5.6.6.2.1, respectively. In addition to these reports, the U.S. Nuclear Regulatory Commission (NRC) staff summarized a conference call with the licensee about the 2011 SG tube inspections in a letter dated June 15, 2011 (ADAMS Accession Number ML 111580515). The NRC staff has completed its review of the submittals pertaining to the BVPS, Unit No.2, SG inspections, and the associated review summary is enclosed. The NRC staff finds that the licensee has provided the information required by the TSs. In addition, the staff did not identify any technical issues that warrant follow-up action at this time. Based on these considerations, the subject TACs are being closed. Please contact me at 301-415-2833, if you have any questions. Sincerely, Ira! Peter Bamford, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-412 Enclosure: As stated cc w/encl: Distribution via Listserv PUBLIC RidsOgcRp Resource LPLI-2 RtF RidsAcrsAcnw_MailCTR Resource RidsNrrDeEsgb Resource AJohnson, NRR RidsRgn1 MailCenter Resource RidsNrrDorlDpr Resource RidsNrrDorlLpl1-2 Resouce RidsNrrPMBeaverValley Resource RidsNrrLAABaxter Resource KKarwoski, NRR ADAMS Accession Number: ML 121290532 | ||
* via email FICE LPLI-2/PM A NRR/ESG ME PBamford GKulsea TE 05/08112 05/16/1205/11/12 OFFICIAL RECORD COPY | |||
}} | |||
By letters dated June 9, 2011 (Agencywide Documents Access and Management System (ADAMS) Accession Number ML 111600250), and September 20,2011 (ADAMS Accession Number ML 112630318), FirstEnergy Nuclear Operating Company (the licensee) submitted information summarizing the results of steam generator (SG) tube inspections at Beaver Valley Power Station (BVPS), Unit No.2. These inspections were performed during the spring 2011 refueling outage. These reports were submitted pursuant to BVPS, Unit No.2, Technical Specifications (TSs) 5.6.6.2.4, and 5.6.6.2.1, respectively. In addition to these reports, the U.S. Nuclear Regulatory Commission (NRC) staff summarized a conference call with the licensee about the 2011 SG tube inspections in a letter dated June 15, 2011 (ADAMS Accession Number ML 111580515). The NRC staff has completed its review of the submittals pertaining to the BVPS, Unit No.2, SG inspections, and the associated review summary is enclosed. The NRC staff finds that the licensee has provided the information required by the TSs. In addition, the staff did not identify any technical issues that warrant follow-up action at this time. Based on these considerations, the subject TACs are being closed. Please contact me at 301-415-2833, if you have any questions. _ Peter Bamford, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-412 | |||
As stated cc w/encl: Distribution via Listserv REVIEW OF THE SPRING 2011 STEAM GENERATOR TUBE INSPECTION REPORT FIRST ENERGY NUCLEAR OPERATING COMPANY BEAVER VALLEY POWER STATION, UNIT 2 DOCKET NO. 50-412 By letters dated June 9, 2011 (Agencywide Documents Access and Management System (ADAMS) Accession Number ML 111600250), and September 20,2011 (ADAMS Accession Number ML 112630318), FirstEnergy Nuclear Operating Company (the licensee) submitted information summarizing the results of the 2011 steam generator (SG) tube inspections at Beaver Valley Power Station (BVPS), Unit NO.2. These inspections were performed during the spring 2011 refueling outage. These reports were submitted pursuant to BVPS, Unit No.2, Technical Specifications (TSs) 5.6.6.2.4, and 5.6.6.2.1, respectively. In addition to these reports, the U.S. Nuclear Regulatory Commission (NRC) staff summarized a conference call with the licensee about these 2011 SG tube inspections in a letter dated June 15, 2011 (ADAMS Accession Number ML 111580515). BVPS, Unit 2, is a 3-loop plant with Westinghouse Model51M SGs. Each SG contains 3376 mill-annealed, Alloy 600 tubes with a nominal outside diameter of 0.875 inches, and a nominal wall thickness of 0.050 inches. The tubes are supported by a number of carbon steel tube support plates and Alloy 600 anti-vibration bars. The tubes were roll expanded at both ends for the full depth of the tubesheet. The entire length of tube within the tubesheet was shot-peened on both the hot-leg and cold-leg side of the SG, prior to operation. In addition, the U-bend region of the small radius tubes were in-situ stress relieved prior to operation. The licensee provided the scope, extent, methods, and results of their steam generator tube inspections in the documents referenced above. In addition, the licensee described corrective actions (Le., tube plugging or repair) taken in response to the inspection findings. Based on the NRC staffs review of the information submitted by the licensee, the staff has the following observation: A tube in Row 29, Column 12, of SG "C" had sporadic permeability variations between the 4th cold-leg and 7th hot-leg tube support plates, which could not be adequately compensated for by magnetically biased bobbin or +PtŽ probes. As a result, the licensee in-situ pressure tested the entire tube. The tube passed the in-situ pressure test and was then stabilized and plugged. Based on a review of the information provided, the NRC staff concludes that the licensee provided the information required by the BVPS, Unit No.2, TSs. In addition, the staff concludes that there are no technical issues that warrant follow-up action at this time, since the inspections appear to be consistent with the objective of detecting potential tube degradation and the inspection results appear to be consistent with industry operating experience at similarly designed and operated units. Enclosure May 16, 2012 Mr. Paul}} | |||
Revision as of 02:11, 2 April 2018
| ML121290532 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 05/16/2012 |
| From: | Bamford P J Plant Licensing Branch 1 |
| To: | Harden P A FirstEnergy Nuclear Operating Co |
| Bamford, Peter J., NRR/DORL 415-2833 | |
| References | |
| TAC ME7382, TAC ME7383 | |
| Download: ML121290532 (3) | |
Text
UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 May 16, 2012 Mr. Paul A. Harden Site Vice President FirstEnergy Nuclear Operating Company Beaver Valley Power Station Mail Stop A-BV-SEB1 P.O. Box 4, Route 168 Shippingport, PA 15077 SUB..BEAVER VALLEY POWER STATION, UNIT NO.2 -REVIEW OF STEAM GENERATOR TUBE INSPECTION REPORT FOR SPRING 2011 REFUELING OUTAGE (TAC NOS. ME7382 AND ME7383) Dear Mr. Harden: By letters dated June 9, 2011 (Agencywide Documents Access and Management System (ADAMS) Accession Number ML 111600250), and September 20,2011 (ADAMS Accession Number ML 112630318), FirstEnergy Nuclear Operating Company (the licensee) submitted information summarizing the results of steam generator (SG) tube inspections at Beaver Valley Power Station (BVPS), Unit No.2. These inspections were performed during the spring 2011 refueling outage. These reports were submitted pursuant to BVPS, Unit No.2, Technical Specifications (TSs) 5.6.6.2.4, and 5.6.6.2.1, respectively. In addition to these reports, the U.S. Nuclear Regulatory Commission (NRC) staff summarized a conference call with the licensee about the 2011 SG tube inspections in a letter dated June 15, 2011 (ADAMS Accession Number ML 111580515). The NRC staff has completed its review of the submittals pertaining to the BVPS, Unit No.2, SG inspections, and the associated review summary is enclosed. The NRC staff finds that the licensee has provided the information required by the TSs. In addition, the staff did not identify any technical issues that warrant follow-up action at this time. Based on these considerations, the subject TACs are being closed. Please contact me at 301-415-2833, if you have any questions. _ Peter Bamford, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-412 Enclosure: As stated cc w/encl: Distribution via Listserv REVIEW OF THE SPRING 2011 STEAM GENERATOR TUBE INSPECTION REPORT FIRST ENERGY NUCLEAR OPERATING COMPANY BEAVER VALLEY POWER STATION, UNIT 2 DOCKET NO. 50-412 By letters dated June 9, 2011 (Agencywide Documents Access and Management System (ADAMS) Accession Number ML 111600250), and September 20,2011 (ADAMS Accession Number ML 112630318), FirstEnergy Nuclear Operating Company (the licensee) submitted information summarizing the results of the 2011 steam generator (SG) tube inspections at Beaver Valley Power Station (BVPS), Unit NO.2. These inspections were performed during the spring 2011 refueling outage. These reports were submitted pursuant to BVPS, Unit No.2, Technical Specifications (TSs) 5.6.6.2.4, and 5.6.6.2.1, respectively. In addition to these reports, the U.S. Nuclear Regulatory Commission (NRC) staff summarized a conference call with the licensee about these 2011 SG tube inspections in a letter dated June 15, 2011 (ADAMS Accession Number ML 111580515). BVPS, Unit 2, is a 3-loop plant with Westinghouse Model51M SGs. Each SG contains 3376 mill-annealed, Alloy 600 tubes with a nominal outside diameter of 0.875 inches, and a nominal wall thickness of 0.050 inches. The tubes are supported by a number of carbon steel tube support plates and Alloy 600 anti-vibration bars. The tubes were roll expanded at both ends for the full depth of the tubesheet. The entire length of tube within the tubesheet was shot-peened on both the hot-leg and cold-leg side of the SG, prior to operation. In addition, the U-bend region of the small radius tubes were in-situ stress relieved prior to operation. The licensee provided the scope, extent, methods, and results of their steam generator tube inspections in the documents referenced above. In addition, the licensee described corrective actions (Le., tube plugging or repair) taken in response to the inspection findings. Based on the NRC staffs review of the information submitted by the licensee, the staff has the following observation: A tube in Row 29, Column 12, of SG "C" had sporadic permeability variations between the 4th cold-leg and 7th hot-leg tube support plates, which could not be adequately compensated for by magnetically biased bobbin or +PtŽ probes. As a result, the licensee in-situ pressure tested the entire tube. The tube passed the in-situ pressure test and was then stabilized and plugged. Based on a review of the information provided, the NRC staff concludes that the licensee provided the information required by the BVPS, Unit No.2, TSs. In addition, the staff concludes that there are no technical issues that warrant follow-up action at this time, since the inspections appear to be consistent with the objective of detecting potential tube degradation and the inspection results appear to be consistent with industry operating experience at similarly designed and operated units. Enclosure May 16, 2012 Mr. Paul A. Harden Site Vice President FirstEnergy Nuclear Operating Company Beaver Valley Power Station Mail Stop A-BV-SEB1 P.O. Box 4, Route 168 Shippingport, PA 15077 BEAVER VALLEY POWER STATION, UNIT NO.2 -REVIEW OF STEAM GENERATOR TUBE INSPECTION REPORT FOR SPRING 2011 REFUELING OUTAGE (TAC NOS. ME7382 AND ME7383) Dear Mr. Harden: By letters dated June 9,2011 (Agencywide Documents Access and Management System (ADAMS) Accession Number ML 111600250), and September 20,2011 (ADAMS Accession Number ML 112630318), FirstEnergy Nuclear Operating Company (the licensee) submitted information summarizing the results of steam generator (SG) tube inspections at Beaver Valley Power Station (BVPS), Unit NO.2. These inspections were performed during the spring 2011 refueling outage. These reports were submitted pursuant to BVPS, Unit No.2, Technical Specifications (TSs) 5.6.6.2.4, and 5.6.6.2.1, respectively. In addition to these reports, the U.S. Nuclear Regulatory Commission (NRC) staff summarized a conference call with the licensee about the 2011 SG tube inspections in a letter dated June 15, 2011 (ADAMS Accession Number ML 111580515). The NRC staff has completed its review of the submittals pertaining to the BVPS, Unit No.2, SG inspections, and the associated review summary is enclosed. The NRC staff finds that the licensee has provided the information required by the TSs. In addition, the staff did not identify any technical issues that warrant follow-up action at this time. Based on these considerations, the subject TACs are being closed. Please contact me at 301-415-2833, if you have any questions. Sincerely, Ira! Peter Bamford, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-412 Enclosure: As stated cc w/encl: Distribution via Listserv PUBLIC RidsOgcRp Resource LPLI-2 RtF RidsAcrsAcnw_MailCTR Resource RidsNrrDeEsgb Resource AJohnson, NRR RidsRgn1 MailCenter Resource RidsNrrDorlDpr Resource RidsNrrDorlLpl1-2 Resouce RidsNrrPMBeaverValley Resource RidsNrrLAABaxter Resource KKarwoski, NRR ADAMS Accession Number: ML 121290532
- via email FICE LPLI-2/PM A NRR/ESG ME PBamford GKulsea TE 05/08112 05/16/1205/11/12 OFFICIAL RECORD COPY