|
---|
Category:Letter
MONTHYEARIR 05000334/20244032024-11-13013 November 2024 Cybersecurity Problem Identification and Resolution Inspection Report 05000334/2024403 and 05000412/2024403 (Cover Letter Only) IR 05000334/20240032024-11-13013 November 2024 Integrated Inspection Report 05000334/2024003 & 05000412/2024003 IR 05000334/20240112024-10-17017 October 2024 License Renewal Phase IV Inspection Report 05000334/2024011 L-24-223, Discharge Monitoring Report (NPDES) Permit No. PA00256152024-09-26026 September 2024 Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-24-038, License Amendment Request to Remove the Expired One-Time Action for Valve Leak Repair in Technical Specification (TS) 3.5.2 and to Correct Core Operating Limits Rep Ort (COLR) References2024-09-17017 September 2024 License Amendment Request to Remove the Expired One-Time Action for Valve Leak Repair in Technical Specification (TS) 3.5.2 and to Correct Core Operating Limits Rep Ort (COLR) References ML24134A1522024-09-17017 September 2024 Exemption from the Requirements of 10 CFR 50.71(e)(4) Final Safety Analysis Report Update Schedule (EPID L-2024-LLE-0005) - Letter L-24-015, Twenty-Ninth Refueling Outage Inservice Inspection Summary Report2024-09-17017 September 2024 Twenty-Ninth Refueling Outage Inservice Inspection Summary Report ML24260A1912024-09-16016 September 2024 Operator Licensing Examination Approval IR 05000334/20240052024-08-29029 August 2024 Updated Inspection Plan for Beaver Valley Power Station, Units 1 and 2 (Reports 05000334/2024005 and 05000412/2024005) L-24-188, Submittal of Quality Assurance Program Manual, Revision 302024-08-27027 August 2024 Submittal of Quality Assurance Program Manual, Revision 30 L-24-199, Discharge Monitoring Report (NPDES) Permit No. PA00256152024-08-22022 August 2024 Discharge Monitoring Report (NPDES) Permit No. PA0025615 IR 05000334/20244022024-08-22022 August 2024 Security Baseline Inspection Report 05000334/2024402 and 05000412/2024402 (Cover Letter Only) L-24-186, Response to RAI for Exemption Request from 10 CFR 50.71(e)(4) Final Safety Analysis Update Schedule2024-08-15015 August 2024 Response to RAI for Exemption Request from 10 CFR 50.71(e)(4) Final Safety Analysis Update Schedule IR 05000334/20240022024-08-0505 August 2024 Integrated Inspection Report 05000334/2024002 and 05000412/2024002 ML24208A0462024-07-26026 July 2024 NRC Office of Investigations Case No. 1-2023-005 L-24-182, Discharge Monitoring Report (NPDES) Permit No. PA00256152024-07-23023 July 2024 Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-24-161, Discharge Monitoring Report (NPDES) Permit No. PA00256152024-07-19019 July 2024 Discharge Monitoring Report (NPDES) Permit No. PA0025615 05000334/LER-2024-004, Reactor Trip Due to Bypass Feedwater Regulating Valve Failure to Control2024-07-17017 July 2024 Reactor Trip Due to Bypass Feedwater Regulating Valve Failure to Control ML24193A2912024-07-16016 July 2024 Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule L-24-014, Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling Svstem Evaluation Models2024-07-16016 July 2024 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling Svstem Evaluation Models IR 05000334/20245012024-07-0808 July 2024 Emergency Preparedness Biennial Exercise Inspection Report 05000334/2024501 and 05000412/2024501 05000334/LER-2024-003, Unanalyzed Containment Bypass Condition Due to Degraded River Water Piping2024-07-0202 July 2024 Unanalyzed Containment Bypass Condition Due to Degraded River Water Piping L-24-164, BV-2, Post Accident Monitor Report2024-06-27027 June 2024 BV-2, Post Accident Monitor Report IR 05000334/20244012024-06-26026 June 2024 Material Control and Accounting Program Inspection Report 05000334/2024401 and 05000412/2024401 (Cover Letter Only) L-24-094, Reactor Vessel Surveillance Capsule Withdrawal Schedule2024-06-24024 June 2024 Reactor Vessel Surveillance Capsule Withdrawal Schedule L-24-152, Response to NRC Regulatory Issue Summary 2024-01 Preparation and Scheduling of Operator Licensing Examinations2024-06-17017 June 2024 Response to NRC Regulatory Issue Summary 2024-01 Preparation and Scheduling of Operator Licensing Examinations 05000334/LER-2024-002, Automatic Reactor Trip Due to Low Reactor Coolant Flow Caused by Transformer Overexcitation Protection Relay Actuation2024-06-11011 June 2024 Automatic Reactor Trip Due to Low Reactor Coolant Flow Caused by Transformer Overexcitation Protection Relay Actuation 05000334/LER-2024-001, Offsite AC Power Source Inoperable Due to Breaker Failure Resulting in Condition Prohibited by Technical Specification2024-06-0606 June 2024 Offsite AC Power Source Inoperable Due to Breaker Failure Resulting in Condition Prohibited by Technical Specification ML24135A1702024-05-29029 May 2024 – Steam Generator Tube Inspection - Review of the Spring 2023 Tube Inspection Reports ML24135A2282024-05-29029 May 2024 Review of the Spring 2023 Outage Generic Letter 95-05 Voltage-Based Alternate Repair Criteria and Steam Generator F Star Reports L-24-121, Discharge Monitoring Report (NPDES) Permit No. PA00256152024-05-23023 May 2024 Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-24-021, Cycle 30 Core Operating Limits Report2024-05-23023 May 2024 Cycle 30 Core Operating Limits Report ML24141A1052024-05-20020 May 2024 Senior Reactor and Reactor Operator Initial License Examinations IR 05000334/20240102024-05-15015 May 2024 Information Request for Quadrennial Baseline Comprehensive Engineering Team Inspection; Notification to Perform Inspection 05000334/2024010 and 05000412/2024010 L-24-107, CFR 50.55a Request 1-TYP-5-RRP-l, for Alternative Method of Nondestructive Examination for River Water Outlet Piping Weld Repair2024-05-13013 May 2024 CFR 50.55a Request 1-TYP-5-RRP-l, for Alternative Method of Nondestructive Examination for River Water Outlet Piping Weld Repair IR 05000334/20240012024-05-0808 May 2024 Integrated Inspection Report 05000334/2024001 and 05000412/2024001 L-23-269, Application to Revise Technical Specifications to Adopt TSTF-569, Revision of Response Time Testing Definitions2024-05-0707 May 2024 Application to Revise Technical Specifications to Adopt TSTF-569, Revision of Response Time Testing Definitions L-24-054, Submittal of 2023 Annual Radioactive Effluent Release Report 2023 Annual Radiological Environmental Operating Report and 2023 Annual Environmental Operating Report (Non-Radiological)2024-04-29029 April 2024 Submittal of 2023 Annual Radioactive Effluent Release Report 2023 Annual Radiological Environmental Operating Report and 2023 Annual Environmental Operating Report (Non-Radiological) L-24-089, Emergency Preparedness Plan2024-04-23023 April 2024 Emergency Preparedness Plan L-24-088, Discharge Monitoring Report (NPDES) Permit No. PA0025615 for March 20242024-04-22022 April 2024 Discharge Monitoring Report (NPDES) Permit No. PA0025615 for March 2024 ML24101A2752024-04-10010 April 2024 Response to Request for Additional Information Regarding Spring 2023 180-Day Steam Generator Tube Inspection Report L-24-082, Withdrawal of Exemption Request2024-04-0303 April 2024 Withdrawal of Exemption Request L-24-013, Annual Notification of Property Insurance Coverage2024-03-26026 March 2024 Annual Notification of Property Insurance Coverage L-24-064, Submittal of Discharge Monitoring Report (NPDES) Permit No. PA00256152024-03-13013 March 2024 Submittal of Discharge Monitoring Report (NPDES) Permit No. PA0025615 ML24044A0662024-03-0404 March 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0083 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting ML24057A0752024-03-0101 March 2024 The Associated Independent Spent Fuel Storage Installations IR 05000334/20230062024-02-28028 February 2024 Annual Assessment Letter for Beaver Valley Power Station, Units 1 and 2 (Reports 05000334/2023006 and 05000412/2023006) CP-202300502, Notice of Planned Closing of Transaction and Provision of Documents to Satisfy Order Conditions2024-02-23023 February 2024 Notice of Planned Closing of Transaction and Provision of Documents to Satisfy Order Conditions L-23-264, Request for Exemption from 10 CFR 50.71(e)(4) Final Safety Analysis Report Update Schedule2024-02-23023 February 2024 Request for Exemption from 10 CFR 50.71(e)(4) Final Safety Analysis Report Update Schedule L-24-050, Retrospective Premium Guarantee2024-02-22022 February 2024 Retrospective Premium Guarantee 2024-09-26
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION 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..IECT: 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 ML111600250), and September 20,2011 (ADAMS Accession Number ML112630318), 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 ML111580515).
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, _
(~~tkt~
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 ML111600250), and September 20,2011 (ADAMS Accession Number ML112630318), 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 ML111580515).
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 +Pt' 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
SUBJECT:
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 ML111600250), and September 20,2011 (ADAMS Accession Number ML112630318), 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 ML111580515).
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: ML121290532
- via email FICE LPLI-2/PM A NRR/ESG ME PBamford GKulsea TE 05/08112 05/11/12 05/07/12 05/16/12 OFFICIAL RECORD COPY