|
|
| Line 18: |
Line 18: |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:June 8, 2006Mr. James H. LashVice President FirstEnergy Nuclear Operating Company Beaver Valley Power Station | | {{#Wiki_filter:June 8, 2006 Mr. James H. Lash Vice President FirstEnergy Nuclear Operating Company Beaver Valley Power Station P.O. Box 4 Shippingport, PA 15077 |
| | |
| P.O. Box 4 Shippingport, PA 15077 | |
|
| |
|
| ==SUBJECT:== | | ==SUBJECT:== |
| BEAVER VALLEY POWER STATION, UNIT NOS. 1 AND 2 (BVPS-1 AND 2) -INSERVICE INSPECTION (ISI) PROGRAM, REQUEST FOR RELIEF NO. | | BEAVER VALLEY POWER STATION, UNIT NOS. 1 AND 2 (BVPS-1 AND 2) - |
| | INSERVICE INSPECTION (ISI) PROGRAM, REQUEST FOR RELIEF NO. |
| BV3-RV-1 REQUEST FOR ADDITIONAL INFORMATION (RAI) (TAC NOS. | | BV3-RV-1 REQUEST FOR ADDITIONAL INFORMATION (RAI) (TAC NOS. |
| MD1135 AND MD1136) | | MD1135 AND MD1136) |
| Line 29: |
Line 28: |
| ==Dear Mr. Lash:== | | ==Dear Mr. Lash:== |
|
| |
|
| The Nuclear Regulatory Commission (NRC) staff has evaluated your April 7, 2006, subjectrequest for relief from the requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI, to perform an alternative remote mechanized examination for reactor vessel shell-to-flange welds during the third 10-year ISI interval for BVPS-1 and the second 10-year ISI interval for BVPS-2. The NRC staff requires the additionalinformation contained in the enclosed RAI in order to complete its review. As discussed with your staff, we request you respond no later than July 14, 2006, in order for the NRC staff tocomplete its review per your requested schedule. If you have any questions, please contact me at 301-415-1402.Sincerely,/RA/Timothy G. Colburn, Senior Project ManagerPlant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket Nos. 50-334 and 50-412 | | The Nuclear Regulatory Commission (NRC) staff has evaluated your April 7, 2006, subject request for relief from the requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI, to perform an alternative remote mechanized examination for reactor vessel shell-to-flange welds during the third 10-year ISI interval for BVPS-1 and the second 10-year ISI interval for BVPS-2. The NRC staff requires the additional information contained in the enclosed RAI in order to complete its review. As discussed with your staff, we request you respond no later than July 14, 2006, in order for the NRC staff to complete its review per your requested schedule. |
| | If you have any questions, please contact me at 301-415-1402. |
| | Sincerely, |
| | /RA/ |
| | Timothy G. Colburn, Senior Project Manager Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-334 and 50-412 |
|
| |
|
| ==Enclosure:== | | ==Enclosure:== |
| RAIcc w/encl: See next page June 8, 2006Mr. James H. LashVice President FirstEnergy Nuclear Operating Company Beaver Valley Power Station
| |
|
| |
|
| P.O. Box 4 Shippingport, PA 15077 | | RAI cc w/encl: See next page |
| | |
| | June 8, 2006 Mr. James H. Lash Vice President FirstEnergy Nuclear Operating Company Beaver Valley Power Station P.O. Box 4 Shippingport, PA 15077 |
|
| |
|
| ==SUBJECT:== | | ==SUBJECT:== |
| BEAVER VALLEY POWER STATION, UNIT NOS. 1 AND 2 (BVPS-1 AND 2) -INSERVICE INSPECTION (ISI) PROGRAM, REQUEST FOR RELIEF NO. | | BEAVER VALLEY POWER STATION, UNIT NOS. 1 AND 2 (BVPS-1 AND 2) - |
| | INSERVICE INSPECTION (ISI) PROGRAM, REQUEST FOR RELIEF NO. |
| BV3-RV-1 REQUEST FOR ADDITIONAL INFORMATION (RAI) (TAC NOS. | | BV3-RV-1 REQUEST FOR ADDITIONAL INFORMATION (RAI) (TAC NOS. |
| MD1135 AND MD1136) | | MD1135 AND MD1136) |
| Line 43: |
Line 48: |
| ==Dear Mr. Lash:== | | ==Dear Mr. Lash:== |
|
| |
|
| The Nuclear Regulatory Commission (NRC) staff has evaluated your April 7, 2006, subjectrequest for relief from the requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI, to perform an alternative remote mechanized examination for reactor vessel shell-to-flange welds during the third 10-year ISI interval for BVPS-1 and the second 10-year ISI interval for BVPS-2. The NRC staff requires the additionalinformation contained in the enclosed RAI in order to complete its review. As discussed with your staff, we request you respond no later than July 14, 2006, in order for the NRC staff tocomplete its review per your requested schedule. If you have any questions, please contact me at 301-415-1402.Sincerely,/RA/Timothy G. Colburn, Senior Project ManagerPlant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket Nos. 50-334 and 50-412 | | The Nuclear Regulatory Commission (NRC) staff has evaluated your April 7, 2006, subject request for relief from the requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI, to perform an alternative remote mechanized examination for reactor vessel shell-to-flange welds during the third 10-year ISI interval for BVPS-1 and the second 10-year ISI interval for BVPS-2. The NRC staff requires the additional information contained in the enclosed RAI in order to complete its review. As discussed with your staff, we request you respond no later than July 14, 2006, in order for the NRC staff to complete its review per your requested schedule. |
| | If you have any questions, please contact me at 301-415-1402. |
| | Sincerely, |
| | /RA/ |
| | Timothy G. Colburn, Senior Project Manager Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-334 and 50-412 |
|
| |
|
| ==Enclosure:== | | ==Enclosure:== |
| RAIcc w/encl: See next page DISTRIBUTION
| |
| : PUBLICLPLI-1 R/FRidsNrrDorlLplaRidsNrrPMTColburn RidsOgc RpRidsNrrCvibRidsNrrLASLittle RidsAcrsAcnwMailCenter RBellamy, RIRidsNrrDprAShaikhACCESSION NO. ML061560081*Input received. No substantive changes made.OFFICELPLI-1/PMLPLI-1/LACVIB/BCLPLI-1/BCNAMETColburnSLittleMMitchell*RLaufer DATE6/07/066/08/0606/02/066/08/06OFFICIAL RECORD COPY EnclosureREQUEST FOR ADDITIONAL INFORMATIONFIRSTENERGY NUCLEAR OPERATING COMPANY (FENOC)10-YEAR INTERVAL INSERVICE INSPECTION (ISI) PROGRAMSREQUEST FOR RELIEF NO. BV3-RV-1BEAVER VALLEY POWER STATION, UNIT NOS. 1 AND 2 (BVPS-1 AND 2)DOCKET NOS. 50-334 AND 50-4121.0SCOPEBy letter dated April 7, 2006, FENOC (the licensee) submitted Relief Request No. BV3-RV-1,from the requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code), Section XI, non-destructive examination (NDE) requirements for BVPS-1 and 2.The request for relief is for the third 10-year ISI interval for BVPS-1 and second 10-year ISI interval for BVPS-2, in which BVPS-1 and 2 have adopted the 1989 Edition no Addenda of the ASME Code, Sections XI and V as the examination code of record.In accordance with Title 10 of the Code of Federal Regulations (10 CFR), Part 50, Section 50.55a(a)(3)(i), the licensee has requested relief from using the techniques of Section V, Article 4, as supplemented by Section XI, Appendix I, and augmented by Regulatory Guide (RG) 1.150, Revision 1, when performing volumetric examinations of the reactor vessel shell-to-flange welds. The licensee stated in the subject request for relief that the prescriptive, amplitude-basedultrasonic examination techniques of Section V, Article 4, supplemented by Appendix I, and augmented by RG 1.150, Revision 1 (hereafter referred to as Article 4), are technically inferior to the performance-based techniques specified in the ASME Code 1995 Edition with 1996 Addenda of Section IX, Appendix VIII, Supplements 4 and 6, as modified by 10 CFR 50.55a(b)(2)(xv), and demonstrated through the Electric Power Research Institute Performance Demonstration Initiative Program (Appendix VIII). Furthermore, the licenseestates that performance-based techniques of Appendix VIII are required for all other reactorvessel shell weld examinations, having replaced the Article 4 techniques. The Nuclear Regulatory Commission staff reviewed the information submitted by the licensee,and based on this review, determined that further information is required to complete the evaluation.2.0REQUEST FOR ADDITIONAL INFORMATION1.Please provide the interval between the last inspection and the proposed inspection schedule for both BVPS-1 and 2. 2.Please provide an analysis of round robin test results, in particular PISC II, to supportthe licensee's claim of greater sizing accuracy and defect sensitivity using performance-based tip diffraction techniques qualified by Appendix VIII, Supplements 4 and 6. Beaver Valley Power Station, Unit Nos. 1 and 2 cc:Gary R. LeidichPresident and Chief Nuclear Officer FirstEnergy Nuclear Operating Company Mail Stop A-GO-19 76 South Main Street Akron, OH 44308Joseph J. HaganSenior Vice President of Operations and Chief Operating Officer FirstEnergy Nuclear Operating Company Mail Stop A-GO-14 76 South Main Street Akron, OH 44308Danny L. PaceSenior Vice President, Fleet Engineering FirstEnergy Nuclear Operating Company Mail Stop A-GO-14 76 South Main Street Akron, OH 44308Jeannie M. RinckelVice President, Fleet Oversight FirstEnergy Nuclear Operating Company Mail Stop A-GO-14 76 South Main Street Akron, OH 44308David W. Jenkins, AttorneyFirstEnergy Corporation Mail Stop A-GO-18 76 South Main Street Akron, OH 44308Manager, Fleet LicensingFirstEnergy Nuclear Operating Company Mail Stop A-GHE-107 395 Ghent Road Akron, OH 44333James H. LashVice PresidentFirstEnergy Nuclear Operating Company Beaver Valley Power Station Mail Stop A-BV-SEB1 P.O. Box 4, Route 168 Shippingport, PA 15077Lew W. MyersExecutive Vice President, Special Projects FirstEnergy Nuclear Operating Company Beaver Valley Power Station Mail Stop A-BV-SGRP P.O. Box 4, Route 168 Shippingport, PA 15077Manager, Site Regulatory ComplianceFirstEnergy Nuclear Operating Company Beaver Valley Power Station Mail Stop A-BV-A P.O. Box 4, Route 168 Shippingport, PA 15077Commissioner James R. LewisWest Virginia Division of Labor 749-B, Building No. 6 Capitol Complex Charleston, WV 25305Director, Utilities DepartmentPublic Utilities Commission 180 East Broad Street Columbus, OH 43266-0573Director, Pennsylvania Emergency Management Agency 2605 Interstate Dr.
| |
| Harrisburg, PA 17110-9364Ohio EPA-DERRATTN: Zack A. Clayton P.O. Box 1049 Columbus, OH 43266-0149 Beaver Valley Power Station, Unit Nos. 1 and 2 (continued) cc:
| |
| Dr. Judith JohnsrudEnvironmental Coalition on Nuclear Power Sierra Club 433 Orlando Avenue State College, PA 16803DirectorBureau of Radiation Protection Pennsylvania Department of Environmental Protection Rachel Carson State Office Building P.O. Box 8469 Harrisburg, PA 17105-8469Mayor of the Borough of Shippingport P.O. Box 3 Shippingport, PA 15077Regional Administrator, Region IU.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406Resident InspectorU.S. Nuclear Regulatory Commission
| |
|
| |
|
| P.O. Box 298 Shippingport, PA 15077}} | | RAI cc w/encl: See next page DISTRIBUTION: |
| | PUBLIC LPLI-1 R/F RidsNrrDorlLpla RidsNrrPMTColburn RidsOgc Rp RidsNrrCvib RidsNrrLASLittle RidsAcrsAcnwMailCenter RBellamy, RI RidsNrrDpr AShaikh ACCESSION NO. ML061560081 *Input received. No substantive changes made. |
| | OFFICE LPLI-1/PM LPLI-1/LA CVIB/BC LPLI-1/BC NAME TColburn SLittle MMitchell* RLaufer DATE 6/07/06 6/08/06 06/02/06 6/08/06 OFFICIAL RECORD COPY |
| | |
| | REQUEST FOR ADDITIONAL INFORMATION FIRSTENERGY NUCLEAR OPERATING COMPANY (FENOC) 10-YEAR INTERVAL INSERVICE INSPECTION (ISI) PROGRAMS REQUEST FOR RELIEF NO. BV3-RV-1 BEAVER VALLEY POWER STATION, UNIT NOS. 1 AND 2 (BVPS-1 AND 2) |
| | DOCKET NOS. 50-334 AND 50-412 1.0 SCOPE By letter dated April 7, 2006, FENOC (the licensee) submitted Relief Request No. BV3-RV-1, from the requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code), Section XI, non-destructive examination (NDE) requirements for BVPS-1 and 2. |
| | The request for relief is for the third 10-year ISI interval for BVPS-1 and second 10-year ISI interval for BVPS-2, in which BVPS-1 and 2 have adopted the 1989 Edition no Addenda of the ASME Code, Sections XI and V as the examination code of record. |
| | In accordance with Title 10 of the Code of Federal Regulations (10 CFR), Part 50, Section 50.55a(a)(3)(i), the licensee has requested relief from using the techniques of Section V, Article 4, as supplemented by Section XI, Appendix I, and augmented by Regulatory Guide (RG) 1.150, Revision 1, when performing volumetric examinations of the reactor vessel shell-to-flange welds. |
| | The licensee stated in the subject request for relief that the prescriptive, amplitude-based ultrasonic examination techniques of Section V, Article 4, supplemented by Appendix I, and augmented by RG 1.150, Revision 1 (hereafter referred to as Article 4), are technically inferior to the performance-based techniques specified in the ASME Code 1995 Edition with 1996 Addenda of Section IX, Appendix VIII, Supplements 4 and 6, as modified by 10 CFR 50.55a(b)(2)(xv), and demonstrated through the Electric Power Research Institute Performance Demonstration Initiative Program (Appendix VIII). Furthermore, the licensee states that performance-based techniques of Appendix VIII are required for all other reactor vessel shell weld examinations, having replaced the Article 4 techniques. |
| | The Nuclear Regulatory Commission staff reviewed the information submitted by the licensee, and based on this review, determined that further information is required to complete the evaluation. |
| | 2.0 REQUEST FOR ADDITIONAL INFORMATION |
| | : 1. Please provide the interval between the last inspection and the proposed inspection schedule for both BVPS-1 and 2. |
| | Enclosure |
| | : 2. Please provide an analysis of round robin test results, in particular PISC II, to support the licensees claim of greater sizing accuracy and defect sensitivity using performance-based tip diffraction techniques qualified by Appendix VIII, Supplements 4 and 6. |
| | Beaver Valley Power Station, Unit Nos. 1 and 2 |
| | |
| | cc: |
| | Gary R. Leidich Vice President President and Chief Nuclear Officer FirstEnergy Nuclear Operating Company FirstEnergy Nuclear Operating Company Beaver Valley Power Station Mail Stop A-GO-19 Mail Stop A-BV-SEB1 76 South Main Street P.O. Box 4, Route 168 Akron, OH 44308 Shippingport, PA 15077 Joseph J. Hagan Lew W. Myers Senior Vice President of Operations Executive Vice President, Special Projects and Chief Operating Officer FirstEnergy Nuclear Operating Company FirstEnergy Nuclear Operating Company Beaver Valley Power Station Mail Stop A-GO-14 Mail Stop A-BV-SGRP 76 South Main Street P.O. Box 4, Route 168 Akron, OH 44308 Shippingport, PA 15077 Danny L. Pace Manager, Site Regulatory Compliance Senior Vice President, Fleet Engineering FirstEnergy Nuclear Operating Company FirstEnergy Nuclear Operating Company Beaver Valley Power Station Mail Stop A-GO-14 Mail Stop A-BV-A 76 South Main Street P.O. Box 4, Route 168 Akron, OH 44308 Shippingport, PA 15077 Jeannie M. Rinckel Commissioner James R. Lewis Vice President, Fleet Oversight West Virginia Division of Labor FirstEnergy Nuclear Operating Company 749-B, Building No. 6 Mail Stop A-GO-14 Capitol Complex 76 South Main Street Charleston, WV 25305 Akron, OH 44308 Director, Utilities Department David W. Jenkins, Attorney Public Utilities Commission FirstEnergy Corporation 180 East Broad Street Mail Stop A-GO-18 Columbus, OH 43266-0573 76 South Main Street Akron, OH 44308 Director, Pennsylvania Emergency Management Agency Manager, Fleet Licensing 2605 Interstate Dr. |
| | FirstEnergy Nuclear Operating Company Harrisburg, PA 17110-9364 Mail Stop A-GHE-107 395 Ghent Road Ohio EPA-DERR Akron, OH 44333 ATTN: Zack A. Clayton P.O. Box 1049 Columbus, OH 43266-0149 James H. Lash |
| | |
| | Beaver Valley Power Station, Unit Nos. 1 and 2 (continued) cc: |
| | Dr. Judith Johnsrud Environmental Coalition on Nuclear Power Sierra Club 433 Orlando Avenue State College, PA 16803 Director Bureau of Radiation Protection Pennsylvania Department of Environmental Protection Rachel Carson State Office Building P.O. Box 8469 Harrisburg, PA 17105-8469 Mayor of the Borough of Shippingport P.O. Box 3 Shippingport, PA 15077 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 298 Shippingport, PA 15077}} |
Letter Sequence RAI |
|---|
|
|
MONTHYEARML0615600812006-06-0808 June 2006
(BVPS-1 and 2) - Inservice Inspection (ISI) Program, Request for Relief No. BV3-RV-1 Request for Additional Information (RAI) (TAC Nos. MD1135 and MD1136)
Project stage: RAI
ML0625800182006-10-0606 October 2006
(BVPs-1 and 2), Inservice Inspection (ISI) Program, Request for Relief No. BV3-RV-1 (TAC Nos. MD1135 and MD1136)
Project stage: Other
2006-10-06
[Table View] |
|
|---|
Category:Letter
MONTHYEARIR 05000334/20240112024-10-17017 October 2024
License Renewal Phase IV Inspection Report 05000334/2024011
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-24-038, 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
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
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
ML24193A2912024-07-16016 July 2024
Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule
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)
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
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-24-050, Retrospective Premium Guarantee2024-02-22022 February 2024
Retrospective Premium Guarantee
05000412/LER-2023-003-01, Missile Barrier Door Left Open Resulting in a Loss of Safety Function2024-02-20020 February 2024
Missile Barrier Door Left Open Resulting in a Loss of Safety Function
IR 05000334/20230042024-02-12012 February 2024
Integrated Inspection Report 05000334/2023004 and 05000412/2023004
ML24025A0922024-01-25025 January 2024
Requalification Program Inspection
2024-09-17
[Table view]
Category:Request for Additional Information (RAI)
MONTHYEARML24204A0012024-07-17017 July 2024
NRR E-mail Capture - Request for Additional Information Vistraops Fleet Exemption for the Requirements in 10 CFR 50.71 Pertaining to the Submittal of Updated Final Safety Analysis Reports
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
ML24044A1772024-02-14014 February 2024
RAI for 180 Days Steam Generator Report
ML23143A0272023-05-23023 May 2023
Licensed Operator Positive Fitness-For-Duty Test
ML23125A1462023-05-0505 May 2023
NRR E-mail Capture - Beaver Valley - RAI Regarding Alternative Repair Methods for Reactor Pressure Vessel Head Penetrations
ML23125A1602023-05-0505 May 2023
NRR E-mail Capture - Correction to Beaver Valley - RAI Regarding Alternative Repair Methods for Reactor Pressure Vessel Head Penetrations
ML23122A0342023-05-0202 May 2023
NRR E-mail Capture - Beaver Valley - Request for Additional Information Regarding Unit 1 - 180 Day Steam Generator Tube Inspection Report
ML22312A5912022-11-0808 November 2022
NRR E-mail Capture - Beaver Valley Power Station, Units 1&2 - Request for Additional Information LAR to Consolidate Fuel Decay Time Technical Specifications in a New Limiting Condition for Operation Titled Decay Time
ML22278A0972022-10-0606 October 2022
Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment Request for Fire Protection Program Changes
ML22178A1322022-06-24024 June 2022
Request for Additional Information for Beaver Valley Unit 2 Steam Generator Inspection Report - Fall 2021 Refueling Outage
ML22068A1822022-03-0909 March 2022
NRR E-mail Capture - Beaver Valley Power Station, Units 1 & 2 - Request for Additional Information for License Amendment Request to Revise Technical Specification 3.3.5
ML22013A7512022-01-13013 January 2022
Information Request to Support Triennial Baseline Design-Basis Capability of Power-Operated Valves Inspection; Inspection Report 05000334/2022010 and 05000412/2022010
ML21292A0482021-10-19019 October 2021
Ti 2515/194 Inspection Documentation Request
ML21259A1642021-09-16016 September 2021
NRR E-mail Capture - Request for Additional Information Regarding the LAR for Core Operating Limits
ML21124A1322021-05-0404 May 2021
Notification of Conduct of a Fire Protection Team Inspection
ML21102A1542021-04-0909 April 2021
Request for Additional Information (2nd Round) - Steam Generator Tube Sleeve LAR
ML21082A4942021-03-23023 March 2021
Final RAIs for GL 04-02 Closure (Email)
ML21068A3502021-03-0909 March 2021
Final Request for Additional Information for Reactor Coolant System (RCS) and Pressure and Tempature Limits Report(Ptlr) TS LAR
ML21053A0252021-02-20020 February 2021
NRR E-mail Capture - Request for Additional Information (Rais) - LaSalle Request for Exemption from Pre-Access Drug and Alcohol Testing
ML21015A5762021-01-14014 January 2021
Final RAIs for Steam Generator 180 Day Tube Inspection Report
ML21007A3732021-01-0707 January 2021
NRR E-mail Capture - (External_Sender) (External) Request for Additional Information Regarding License Amendment Request to Incorporate the Applicable Standard Technical Specification 5.2.2, Unit Staff,
ML21004A1442020-12-30030 December 2020
NRR E-mail Capture - Request for Additional Information Regarding License Amendment Request to Incorporate the Applicable Standard Technical Specification 5.2.2, Unit Staff
ML20290B0082020-10-0808 October 2020
Draft Request for Additional Information - Steam Generator Letter
ML20127H8672020-05-0606 May 2020
NRR E-mail Capture - Beaver Valley, Davis-Besse, and Perry - Request for Additional Information Regarding Request for Exemptions from Part 73 Security Requalification Requirements
ML20072N0402020-03-12012 March 2020
Request for Additional Information - Control Envelope Habitability LAR
ML19192A2222019-07-18018 July 2019
Request for Additional Information Regarding Application for Order Consenting to Transfer of Licenses and Conforming License Amendments
ML19143A0732019-05-29029 May 2019
FENOC Fleet - Beaver Valley, Units 1 and 2; Davis-Besse, Unit 1, Perry, Unit 1 - Supplemental Information Needed for Acceptance of Requested Licensing Action; Application for Order Consenting to License Transfer and Conforming Amendments
ML18242A3642018-08-29029 August 2018
Request for Additional Information (Final) -Steam Generator Technical Specification LAR
ML18102B0852018-04-12012 April 2018
NRR E-mail Capture - Follow-up Request for Additional Information (RAI) FENOC FLEET-- Exemption Request for a Physical Barrier Requirement for Beaver
ML18043A0102018-02-0909 February 2018
NRR E-mail Capture - FENOC--MG0010-MG0011, MG-0012, MG0013-- Request for Additional Information (RAI) - Exemption Request Security Barrier in Physical Plans
ML18024B3642018-01-24024 January 2018
NRR E-mail Capture - Beaver Valley 10 CFR 50.54(f) - NTTF 2.1 SPRA Review
ML18019A0722018-01-18018 January 2018
NRR E-mail Capture - Beaver Valley Unit No. 1: Request for Additional Information - Modified Rtpts Values and Reactor Vessel Surveillance Capsule Withdrawal Schedule
ML17353A1582017-12-19019 December 2017
NRR E-mail Capture - Request for Additional Information: Beaver Valley Unit No. 1 - Proposed Alternative Request, 1-TYP-4-BA-01
ML17352B2612017-12-18018 December 2017
NRR E-mail Capture - Request for Additional Information: Beaver Valley Unit No. 1 - Proposed Alternative Request, 1-TYP-4-BA-01
ML17303B1582017-11-0707 November 2017
FENOC-Beaver Valley Power Station, Units 1 and 2, Davis-Besse Nuclear Power Station, Unit 1, Perry Nuclear Power Plant Unit 1 - Generic Letter 2016-01, Request for Supplemental Information
ML17256A2502017-09-13013 September 2017
NRR E-mail Capture - Beaver Valley Power Station Units 1&2: Request for Additional Information for Emergency Plan EAL Change to Adopt NEI 99-01, Rev. 6,
ML17220A2342017-08-0808 August 2017
E-mail Regarding Request for Additional Information for NFPA 805 License Amendment Request
ML17093A7622017-04-10010 April 2017
Request for Additional Information Regarding Emergency Action Level Scheme Change License Amendment Request
ML17031A0362017-02-0303 February 2017
Request for Additional Information Regarding Relief Request Numbers PR6 and PR7
ML16333A0162016-12-0202 December 2016
Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805
ML16147A2842016-06-14014 June 2016
Request for Additional Infomation Regarding Fall 2015 Refueling Steam Generator Tube Inspections
ML16071A1222016-04-0707 April 2016
Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805
ML16084A8442016-03-30030 March 2016
Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805
ML16060A0122016-02-29029 February 2016
FENOC - Email RAI to Licensee Regarding LAR for Changes to TS 5.3.1 CAC Nos. MF7118, MF7119, and MF7120
ML15320A4132015-11-24024 November 2015
Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805
ML15280A0742015-10-0909 October 2015
Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805
ML15279A1252015-10-0505 October 2015
Licensed Operator Positive for Fitness-for-Duty-Test
ML15181A2142015-07-14014 July 2015
Request for Additional Information Regarding License Amendment Request to Revise Steam Generator Technical Specifications to Reflect TSTF-510 and to Revise Alloy 800 Sleeve Technical Specifications (TAC Nos. MF6054 & MF6055)
ML15125A4162015-05-11011 May 2015
Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805 (TAC Nos. MF3301 & MF3302)
ML15016A4392015-01-20020 January 2015
Draft Request for Additional Information
2024-07-17
[Table view] |
Text
June 8, 2006 Mr. James H. Lash Vice President FirstEnergy Nuclear Operating Company Beaver Valley Power Station P.O. Box 4 Shippingport, PA 15077
SUBJECT:
BEAVER VALLEY POWER STATION, UNIT NOS. 1 AND 2 (BVPS-1 AND 2) -
INSERVICE INSPECTION (ISI) PROGRAM, REQUEST FOR RELIEF NO.
BV3-RV-1 REQUEST FOR ADDITIONAL INFORMATION (RAI) (TAC NOS.
MD1135 AND MD1136)
Dear Mr. Lash:
The Nuclear Regulatory Commission (NRC) staff has evaluated your April 7, 2006, subject request for relief from the requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code,Section XI, to perform an alternative remote mechanized examination for reactor vessel shell-to-flange welds during the third 10-year ISI interval for BVPS-1 and the second 10-year ISI interval for BVPS-2. The NRC staff requires the additional information contained in the enclosed RAI in order to complete its review. As discussed with your staff, we request you respond no later than July 14, 2006, in order for the NRC staff to complete its review per your requested schedule.
If you have any questions, please contact me at 301-415-1402.
Sincerely,
/RA/
Timothy G. Colburn, Senior Project Manager Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-334 and 50-412
Enclosure:
RAI cc w/encl: See next page
June 8, 2006 Mr. James H. Lash Vice President FirstEnergy Nuclear Operating Company Beaver Valley Power Station P.O. Box 4 Shippingport, PA 15077
SUBJECT:
BEAVER VALLEY POWER STATION, UNIT NOS. 1 AND 2 (BVPS-1 AND 2) -
INSERVICE INSPECTION (ISI) PROGRAM, REQUEST FOR RELIEF NO.
BV3-RV-1 REQUEST FOR ADDITIONAL INFORMATION (RAI) (TAC NOS.
MD1135 AND MD1136)
Dear Mr. Lash:
The Nuclear Regulatory Commission (NRC) staff has evaluated your April 7, 2006, subject request for relief from the requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code,Section XI, to perform an alternative remote mechanized examination for reactor vessel shell-to-flange welds during the third 10-year ISI interval for BVPS-1 and the second 10-year ISI interval for BVPS-2. The NRC staff requires the additional information contained in the enclosed RAI in order to complete its review. As discussed with your staff, we request you respond no later than July 14, 2006, in order for the NRC staff to complete its review per your requested schedule.
If you have any questions, please contact me at 301-415-1402.
Sincerely,
/RA/
Timothy G. Colburn, Senior Project Manager Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-334 and 50-412
Enclosure:
RAI cc w/encl: See next page DISTRIBUTION:
PUBLIC LPLI-1 R/F RidsNrrDorlLpla RidsNrrPMTColburn RidsOgc Rp RidsNrrCvib RidsNrrLASLittle RidsAcrsAcnwMailCenter RBellamy, RI RidsNrrDpr AShaikh ACCESSION NO. ML061560081 *Input received. No substantive changes made.
OFFICE LPLI-1/PM LPLI-1/LA CVIB/BC LPLI-1/BC NAME TColburn SLittle MMitchell* RLaufer DATE 6/07/06 6/08/06 06/02/06 6/08/06 OFFICIAL RECORD COPY
REQUEST FOR ADDITIONAL INFORMATION FIRSTENERGY NUCLEAR OPERATING COMPANY (FENOC) 10-YEAR INTERVAL INSERVICE INSPECTION (ISI) PROGRAMS REQUEST FOR RELIEF NO. BV3-RV-1 BEAVER VALLEY POWER STATION, UNIT NOS. 1 AND 2 (BVPS-1 AND 2)
DOCKET NOS. 50-334 AND 50-412 1.0 SCOPE By letter dated April 7, 2006, FENOC (the licensee) submitted Relief Request No. BV3-RV-1, from the requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, non-destructive examination (NDE) requirements for BVPS-1 and 2.
The request for relief is for the third 10-year ISI interval for BVPS-1 and second 10-year ISI interval for BVPS-2, in which BVPS-1 and 2 have adopted the 1989 Edition no Addenda of the ASME Code, Sections XI and V as the examination code of record.
In accordance with Title 10 of the Code of Federal Regulations (10 CFR), Part 50, Section 50.55a(a)(3)(i), the licensee has requested relief from using the techniques of Section V, Article 4, as supplemented by Section XI, Appendix I, and augmented by Regulatory Guide (RG) 1.150, Revision 1, when performing volumetric examinations of the reactor vessel shell-to-flange welds.
The licensee stated in the subject request for relief that the prescriptive, amplitude-based ultrasonic examination techniques of Section V, Article 4, supplemented by Appendix I, and augmented by RG 1.150, Revision 1 (hereafter referred to as Article 4), are technically inferior to the performance-based techniques specified in the ASME Code 1995 Edition with 1996 Addenda of Section IX, Appendix VIII, Supplements 4 and 6, as modified by 10 CFR 50.55a(b)(2)(xv), and demonstrated through the Electric Power Research Institute Performance Demonstration Initiative Program (Appendix VIII). Furthermore, the licensee states that performance-based techniques of Appendix VIII are required for all other reactor vessel shell weld examinations, having replaced the Article 4 techniques.
The Nuclear Regulatory Commission staff reviewed the information submitted by the licensee, and based on this review, determined that further information is required to complete the evaluation.
2.0 REQUEST FOR ADDITIONAL INFORMATION
- 1. Please provide the interval between the last inspection and the proposed inspection schedule for both BVPS-1 and 2.
Enclosure
- 2. Please provide an analysis of round robin test results, in particular PISC II, to support the licensees claim of greater sizing accuracy and defect sensitivity using performance-based tip diffraction techniques qualified by Appendix VIII, Supplements 4 and 6.
Beaver Valley Power Station, Unit Nos. 1 and 2
cc:
Gary R. Leidich Vice President President and Chief Nuclear Officer FirstEnergy Nuclear Operating Company FirstEnergy Nuclear Operating Company Beaver Valley Power Station Mail Stop A-GO-19 Mail Stop A-BV-SEB1 76 South Main Street P.O. Box 4, Route 168 Akron, OH 44308 Shippingport, PA 15077 Joseph J. Hagan Lew W. Myers Senior Vice President of Operations Executive Vice President, Special Projects and Chief Operating Officer FirstEnergy Nuclear Operating Company FirstEnergy Nuclear Operating Company Beaver Valley Power Station Mail Stop A-GO-14 Mail Stop A-BV-SGRP 76 South Main Street P.O. Box 4, Route 168 Akron, OH 44308 Shippingport, PA 15077 Danny L. Pace Manager, Site Regulatory Compliance Senior Vice President, Fleet Engineering FirstEnergy Nuclear Operating Company FirstEnergy Nuclear Operating Company Beaver Valley Power Station Mail Stop A-GO-14 Mail Stop A-BV-A 76 South Main Street P.O. Box 4, Route 168 Akron, OH 44308 Shippingport, PA 15077 Jeannie M. Rinckel Commissioner James R. Lewis Vice President, Fleet Oversight West Virginia Division of Labor FirstEnergy Nuclear Operating Company 749-B, Building No. 6 Mail Stop A-GO-14 Capitol Complex 76 South Main Street Charleston, WV 25305 Akron, OH 44308 Director, Utilities Department David W. Jenkins, Attorney Public Utilities Commission FirstEnergy Corporation 180 East Broad Street Mail Stop A-GO-18 Columbus, OH 43266-0573 76 South Main Street Akron, OH 44308 Director, Pennsylvania Emergency Management Agency Manager, Fleet Licensing 2605 Interstate Dr.
FirstEnergy Nuclear Operating Company Harrisburg, PA 17110-9364 Mail Stop A-GHE-107 395 Ghent Road Ohio EPA-DERR Akron, OH 44333 ATTN: Zack A. Clayton P.O. Box 1049 Columbus, OH 43266-0149 James H. Lash
Beaver Valley Power Station, Unit Nos. 1 and 2 (continued) cc:
Dr. Judith Johnsrud Environmental Coalition on Nuclear Power Sierra Club 433 Orlando Avenue State College, PA 16803 Director Bureau of Radiation Protection Pennsylvania Department of Environmental Protection Rachel Carson State Office Building P.O. Box 8469 Harrisburg, PA 17105-8469 Mayor of the Borough of Shippingport P.O. Box 3 Shippingport, PA 15077 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 298 Shippingport, PA 15077