Letter Sequence Supplement |
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Results
Other: L-08-123, Drawing Lr 1-46-2, Rev. 5, Post DBA Hydrogen Analyzer System., L-08-189, Drawing Lr 2-27A-2, Rev. 4, Auxiliary Steam and Condensate System (Ass)., L-08-261, Schedule for Submittal of Annual Update for License Renewal Application, L-08-262, Drawing, Lr Drawing 2-31-1, Rev. 5, Demineralized Water System (Wtd)., L-08-263, Submittal of Revision to License Renewal Application Amendment No. 24, L-08-292, Lr Drawing 1-21-1, Rev. 7, Main Steam System (Ms)., L-08-316, License Renewal Application Amendment No. 26 (TAC Nos. MD6593 and MD6594), Revisions, L-08-393, License Renewal Application, Amendment No. 33, L-09-058, Comments on Safety Evaluation Report with Open Item Related to the License Renewal, L-09-138, License Renewal Application, Amendment No. 36, L-09-151, License Renewal Application Amendment No. 37, ML081000322, ML081000323, ML081000324, ML081000326, ML081000327, ML081000328, ML081000329, ML081000330, ML081000331, ML081000332, ML081640592, ML081640593, ML081640594, ML081640596, ML081640597, ML081640598, ML081640599, ML081640600, ML081640601, ML081640602, ML081640603, ML081640604, ML082550686, ML082550687, ML082550688, ML083010249, ML092740576, ML092920050, NRC-2009-0496, Beaver Valley Federal Register Notice - Record of Decision to Renew License
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MONTHYEARL-07-130, Submittal of Pressure and Temperature Limits Report, Revision 42007-09-19019 September 2007 Submittal of Pressure and Temperature Limits Report, Revision 4 Project stage: Request ML0805902622008-03-0303 March 2008 Request for Additional Information, License Renewal Application (TAC Nos. MD6593 and MD6594) Project stage: RAI ML0806402162008-03-0505 March 2008 RAI for the Review of the Beaver Valley Power Station, Units 1 and 2, LRA Project stage: RAI ML0806010202008-03-0505 March 2008 RAI for the Review of the Beaver Valley Power Station, Units 1 & 2, LRA Project stage: RAI ML0807202882008-03-21021 March 2008 Request for Additional Information, Section B.2.35 Project stage: RAI ML0807907442008-03-26026 March 2008 Request for Additional Information for the Review of the Beaver Valley Power Station, Units 1 and 2, License Renewal Application, for Sections B.2.6, B.2.19, and B.2.23 Project stage: RAI L-08-122, Reply to Request for Additional Information for the Review of the License Renewal Application and Revisions to License Renewal Application Boundary Drawings2008-03-31031 March 2008 Reply to Request for Additional Information for the Review of the License Renewal Application and Revisions to License Renewal Application Boundary Drawings Project stage: Response to RAI ML0807903922008-04-0101 April 2008 RAI for the Review of the Beaver Valley Power Station, Units 1 & 2, LRA Project stage: RAI ML0807905382008-04-0101 April 2008 RAI for the Review of the Beaver Valley Power Station, Units 1 & 2, LRA Project stage: RAI L-08-124, Reply to Request for Additional Information for Review of the License Renewal Application and License Renewal Application Amendment No. 52008-04-0202 April 2008 Reply to Request for Additional Information for Review of the License Renewal Application and License Renewal Application Amendment No. 5 Project stage: Response to RAI ML0807907352008-04-0303 April 2008 RAI for the Reveiw of the Beaver Valley, Units 1 and 2, License Renewal Application Project stage: RAI ML0810002962008-04-0303 April 2008 Reply to Request for Additional Information for the Review of License Renewal Application, Amendment No. 4, and Revised License Renewal Boundary Drawings Project stage: Response to RAI ML0810003222008-04-0303 April 2008 Drawing Lr 1-07-2, Rev. 4, Chemical and Volume Control System. Project stage: Other ML0810003232008-04-0303 April 2008 Drawing Lr 1-07-3, Rev. 6, Chemical and Volume Control System. Project stage: Other ML0810003242008-04-0303 April 2008 Drawing Lr 1-08-1, Rev. 4, Boron Recovery Degasifiers. Project stage: Other ML0810003262008-04-0303 April 2008 Drawing Lr 1-09-2, Rev. 4, Vent and Drain System. Project stage: Other ML0810003272008-04-0303 April 2008 Drawing Lr 1-12-1, Rev. 5, Containment Vacuum and Leakage Monitoring System. Project stage: Other ML0810003282008-04-0303 April 2008 Drawing Lr 1-14A-1, Rev. 7, Sample System. Project stage: Other ML0810003292008-04-0303 April 2008 Drawing Lr 1-14A-2, Rev. 5, Sample System. Project stage: Other ML0810003302008-04-0303 April 2008 Drawing Lr 1-19-1, Rev. 5, Gaseous Waste Disposal System. Project stage: Other ML0810003322008-04-0303 April 2008 Drawing Lr 1-30-1, Rev. 5, River Water System. Project stage: Other L-08-123, Drawing Lr 1-46-2, Rev. 5, Post DBA Hydrogen Analyzer System.2008-04-0303 April 2008 Drawing Lr 1-46-2, Rev. 5, Post DBA Hydrogen Analyzer System. Project stage: Other ML0810003312008-04-0303 April 2008 Drawing Lr 1-24-1, Rev. 6, Feedwater System. Project stage: Other ML0809804832008-04-17017 April 2008 Request for Additional Information, Review of License Renewal Application Project stage: RAI ML0810503332008-04-17017 April 2008 Request for Additional Information, Review of License Renewal Application Project stage: RAI L-08-143, Reply to Request for Additional Information for Review of License Renewal Application and License Renewal Application Amendment No. 62008-04-18018 April 2008 Reply to Request for Additional Information for Review of License Renewal Application and License Renewal Application Amendment No. 6 Project stage: Response to RAI L-08-144, Reply to Request for Additional Information for the Review of License Renewal Application2008-04-25025 April 2008 Reply to Request for Additional Information for the Review of License Renewal Application Project stage: Response to RAI ML0811303942008-04-28028 April 2008 Request for Additional Information, Review of License Renewal Application Project stage: RAI ML0810502702008-04-30030 April 2008 Request for Additional Information for the Review of the Beaver Valley Power Station, Units 1 and 2, License Renewal Application Project stage: RAI L-08-146, Reply to Request for Additional Information for Review, License Renewal Application and License Renewal Application Amendment No. 72008-04-30030 April 2008 Reply to Request for Additional Information for Review, License Renewal Application and License Renewal Application Amendment No. 7 Project stage: Response to RAI L-08-174, Request for Revised Submittal Date for Reply to Request for Additional Information for the Review of the License Renewal Application2008-05-0202 May 2008 Request for Revised Submittal Date for Reply to Request for Additional Information for the Review of the License Renewal Application Project stage: Response to RAI L-08-149, Reply to Request for Additional Information for the Review of the Beaver Valley Power Station, Units 1 and 2, License Renewal Application2008-05-0505 May 2008 Reply to Request for Additional Information for the Review of the Beaver Valley Power Station, Units 1 and 2, License Renewal Application Project stage: Response to RAI ML0814104162008-05-0808 May 2008 Transmittal of Correction to Reply to RAI for the Review of License Renewal Application, License Renewal Application Amendment No. 8 & Revised License Renewal Boundary Drawings Project stage: Request ML0810505432008-05-0808 May 2008 Request for Additional Information, Sections 3.5.2.2, B.2.1, B.2.3 and 4.6 of License Renewal Application Project stage: RAI ML0811604672008-05-0808 May 2008 Request for Additional Information for the Review of the Beaver Valley Power Station, Units 1 and 2, License Renewal Application Project stage: RAI ML0812009202008-05-0808 May 2008 Request for Additional Information for the Review of the Beaver Valley Power Station, Units 1 and 2, License Renewal Application (TAC MD6593 and MD6594) Project stage: RAI ML0811205392008-05-15015 May 2008 Request for Additional Information, License Renewal Application (TAC Nos. MD6593 and MD6594) Project stage: RAI ML0814405432008-05-19019 May 2008 Reply to Request for Additional Information for the Review of the License Renewal Application Amendment No. 9. and Revised License Renewal Boundary Drawings Project stage: Response to RAI L-08-169, Reply to Request for Additional Information for the Review of the Beaver Valley Power Station, Units 1 and 2, License Renewal Application2008-05-19019 May 2008 Reply to Request for Additional Information for the Review of the Beaver Valley Power Station, Units 1 and 2, License Renewal Application Project stage: Response to RAI ML0811304122008-05-22022 May 2008 Request for Additional Information for the Review of the Beaver Valley Power Station, Units 1 and 2, License Renewal Application Project stage: RAI ML0813605572008-05-22022 May 2008 Revision of Schedule for the Conduct of Review of the Beaver Valley Power Station, Units 1 and 2, License Renewal Application Project stage: Approval ML0811505772008-05-28028 May 2008 Request for Additional Information for Sections B.2.27, 4.3 and 4.7.4 of the BVPS LRA Project stage: RAI L-08-180, Reply to Request for Additional Information for the Review of the License Renewal Application2008-05-28028 May 2008 Reply to Request for Additional Information for the Review of the License Renewal Application Project stage: Response to RAI L-08-147, Reply to Request for Additional Information for Renewal License Application2008-06-0202 June 2008 Reply to Request for Additional Information for Renewal License Application Project stage: Response to RAI ML0814306872008-06-0404 June 2008 Request for Additional Information the Review of Beaver Valley, Units 1 and 2, License Renewal Application Project stage: RAI L-08-181, Reply to Request for Additional Information for the Review of the License Renewal Application and License Renewal Application, Amendment No. 102008-06-0606 June 2008 Reply to Request for Additional Information for the Review of the License Renewal Application and License Renewal Application, Amendment No. 10 Project stage: Response to RAI ML0816405052008-06-0909 June 2008 Reply to Request for Additional Information for the Review of the License Renewal Application License Renewal Application Amendment No. 11, and Revised License Renewal Boundary Drawings Project stage: Response to RAI ML0816405922008-06-0909 June 2008 Drawing Lr 1-14A-1, Rev. 8, Sample System (Ss). Project stage: Other ML0816405932008-06-0909 June 2008 Drawing Lr 1-21-1, Rev. 6, Main Steam System (Ms). Project stage: Other ML0816405942008-06-0909 June 2008 Drawing Lr 1-22-1, Rev. 4, Condensate System (Cn). Project stage: Other 2008-04-03
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Category:Letter type:L
MONTHYEARL-24-161, Discharge Monitoring Report (NPDES) Permit No. PA00256152024-07-19019 July 2024 Discharge Monitoring Report (NPDES) Permit No. PA0025615 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 L-24-164, BV-2, Post Accident Monitor Report2024-06-27027 June 2024 BV-2, Post Accident Monitor Report 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 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 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 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 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 L-24-050, Retrospective Premium Guarantee2024-02-22022 February 2024 Retrospective Premium Guarantee L-23-267, Submittal of Discharge Monitoring Report (Npdes), Permit No. PA00256152023-12-18018 December 2023 Submittal of Discharge Monitoring Report (Npdes), Permit No. PA0025615 L-23-229, Request for Additional Information Regarding the Spring 2023 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria and Steam Generator F-Star Reports2023-11-29029 November 2023 Request for Additional Information Regarding the Spring 2023 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria and Steam Generator F-Star Reports L-23-247, Discharge Monitoring Report (NPDES) Permit No. PA00256152023-11-17017 November 2023 Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-23-227, Discharge Monitoring Report (NPDES) Permit No. PA0025615 for Third Quarter 20232023-10-20020 October 2023 Discharge Monitoring Report (NPDES) Permit No. PA0025615 for Third Quarter 2023 L-23-208, Submittal of Discharge Monitoring Report Cnpdes), Permit No. PA00256152023-09-14014 September 2023 Submittal of Discharge Monitoring Report Cnpdes), Permit No. PA0025615 L-23-167, Twenty-Third Refueling Outage Inservice Inspection Summary Report2023-09-13013 September 2023 Twenty-Third Refueling Outage Inservice Inspection Summary Report L-23-205, Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-09-12012 September 2023 Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments L-23-172, Quality Assurance Program Manual2023-08-31031 August 2023 Quality Assurance Program Manual L-23-188, Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-08-0707 August 2023 Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments L-23-179, Submittal of Discharge Monitoring Report, (NPDES) Permit No. PA00256152023-07-18018 July 2023 Submittal of Discharge Monitoring Report, (NPDES) Permit No. PA0025615 L-23-165, Discharge Monitoring Report (NPDES) Permit No. PA00256152023-06-26026 June 2023 Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-23-139, Response to Request for Additional Information Regarding Fall 2022 180-Day Steam Generator Tube Inspection Report2023-06-13013 June 2023 Response to Request for Additional Information Regarding Fall 2022 180-Day Steam Generator Tube Inspection Report L-23-055, Submittal of the Updated Final Safety Analysis Report, Revision 342023-05-23023 May 2023 Submittal of the Updated Final Safety Analysis Report, Revision 34 L-23-065, Annual Financial Report2023-05-22022 May 2023 Annual Financial Report L-23-137, Discharge Monitoring Report (NPDES) Permit No. PA00256152023-05-18018 May 2023 Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-23-125, Cycle 24 Core Operating Limits Report2023-05-17017 May 2023 Cycle 24 Core Operating Limits Report L-23-132, Response to NRC Regulatory Issue Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations2023-05-10010 May 2023 Response to NRC Regulatory Issue Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations L-23-129, Response to Request for Additional Information for 10 CFR 50.55a Request 2-TYP-4-RV-06 for Alternative Repair Methods for Reactor Pressure Vessel Head Penetrations2023-05-0505 May 2023 Response to Request for Additional Information for 10 CFR 50.55a Request 2-TYP-4-RV-06 for Alternative Repair Methods for Reactor Pressure Vessel Head Penetrations L-23-115, Submittal of 2022 Annual Radioactive Effluent Release Report, 2022 Annual Radiological Environmental Operating Report, and 2022 Annual Environmental Operating Report (Non-Radiological2023-04-27027 April 2023 Submittal of 2022 Annual Radioactive Effluent Release Report, 2022 Annual Radiological Environmental Operating Report, and 2022 Annual Environmental Operating Report (Non-Radiological L-23-126, Discharge Monitoring Report (Npdes), Permit No. PA00256152023-04-22022 April 2023 Discharge Monitoring Report (Npdes), Permit No. PA0025615 L-23-053, 2022 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2023-04-14014 April 2023 2022 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models L-23-061, Submittal of the Decommissioning Funding Status Reports2023-03-31031 March 2023 Submittal of the Decommissioning Funding Status Reports L-23-058, 180-Day Steam Generator Tube Inspection Report2023-03-27027 March 2023 180-Day Steam Generator Tube Inspection Report L-23-066, Annual Notification of Property Insurance Coverage2023-03-21021 March 2023 Annual Notification of Property Insurance Coverage L-23-036, Report of Facility Changes, Tests and Experiments2023-03-13013 March 2023 Report of Facility Changes, Tests and Experiments L-23-087, Supplement to Emergency License Amendment Request for Technical Specification 3.5.2 Regarding One-Time Action for Valve Leak Repair (L-2023-LLA-0027)2023-03-0404 March 2023 Supplement to Emergency License Amendment Request for Technical Specification 3.5.2 Regarding One-Time Action for Valve Leak Repair (L-2023-LLA-0027) L-23-086, Response to Request for Additional Information for Emergency License Amendment Request for Technical Specification 3.5.2 Regarding One-Time Action for Valve Leak Repair2023-03-0404 March 2023 Response to Request for Additional Information for Emergency License Amendment Request for Technical Specification 3.5.2 Regarding One-Time Action for Valve Leak Repair L-23-073, Emergency License Amendment Request for Technical Specification 3.5.2 Regarding One-Time Action for Valve Leak Repair2023-03-0101 March 2023 Emergency License Amendment Request for Technical Specification 3.5.2 Regarding One-Time Action for Valve Leak Repair L-23-064, Discharge Monitoring Report, (NPDES) Permit No. PA00256152023-02-21021 February 2023 Discharge Monitoring Report, (NPDES) Permit No. PA0025615 L-23-016, Twenty-Eighth Refueling Outage Inservice Inspection Summary Report2023-02-21021 February 2023 Twenty-Eighth Refueling Outage Inservice Inspection Summary Report L-23-057, Energy Harbor Nuclear Corp Retrospective Premium Guarantee2023-02-20020 February 2023 Energy Harbor Nuclear Corp Retrospective Premium Guarantee L-22-286, Supplement to Request for an Amendment to Consolidate Fuel Decay Time Technical Specifications in a New Limiting Condition for Operation Titled Decay Time2023-02-14014 February 2023 Supplement to Request for an Amendment to Consolidate Fuel Decay Time Technical Specifications in a New Limiting Condition for Operation Titled Decay Time L-22-193, Request for Exemption from Specific Provisions in 10 CFR 50 Appendix H2023-02-14014 February 2023 Request for Exemption from Specific Provisions in 10 CFR 50 Appendix H L-23-032, Discharge Monitoring Report (NPDES) Permit No. PA0025615 for Second Half of 20222023-01-23023 January 2023 Discharge Monitoring Report (NPDES) Permit No. PA0025615 for Second Half of 2022 2024-07-19
[Table view] Category:License-Application for (Amend/Renewal/New) for DKT 30
[Table view] Category:40
MONTHYEARL-23-061, Submittal of the Decommissioning Funding Status Reports2023-03-31031 March 2023 Submittal of the Decommissioning Funding Status Reports L-21-046, Submittal of the Decommissioning Funding Status Reports for Beaver Valley Power Station, Unit Nos. 1 and 2, Davis-Besse Nuclear Power Station, and Perry Nuclear Power Plant2021-03-29029 March 2021 Submittal of the Decommissioning Funding Status Reports for Beaver Valley Power Station, Unit Nos. 1 and 2, Davis-Besse Nuclear Power Station, and Perry Nuclear Power Plant ML17114A0622017-04-24024 April 2017 Supplemental Information Regarding Decommissioning Funding Status Report L-17-028, Submittal of the Decommissioning Funding Status Reports2017-03-24024 March 2017 Submittal of the Decommissioning Funding Status Reports L-15-327, ISFSI; Davis-Besse, Unit 1 & ISFSI and Perry, Unit 1 & ISFSI - Triennial ISFSI Decommissioning Funding Plans2015-12-0909 December 2015 ISFSI; Davis-Besse, Unit 1 & ISFSI and Perry, Unit 1 & ISFSI - Triennial ISFSI Decommissioning Funding Plans L-15-101, Submittal of the Decommissioning Funding Status Reports for Beaver Valley, Units 1 and 2, Davis-Besse and Perry, Unit 12015-03-31031 March 2015 Submittal of the Decommissioning Funding Status Reports for Beaver Valley, Units 1 and 2, Davis-Besse and Perry, Unit 1 L-14-303, ISFSI, Submittal of Decommissioning Funding Plan2014-12-0808 December 2014 ISFSI, Submittal of Decommissioning Funding Plan L-11-102, Submittal of the Decommissioning Reports2011-03-29029 March 2011 Submittal of the Decommissioning Reports L-09-187, Supplemental Information for Decommissioning Funding Report2009-07-28028 July 2009 Supplemental Information for Decommissioning Funding Report L-09-064, Submittal of Decommissioning Reports for Year Ending December 31, 20082009-03-27027 March 2009 Submittal of Decommissioning Reports for Year Ending December 31, 2008 L-08-332, Supplemental Information for the Review of the Beaver Valley Power Station, Units 1 and 2. License Renewal Application (TAC Nos. MD6593 and MD6594) and License Renewal Application Amendment No. 302008-11-0505 November 2008 Supplemental Information for the Review of the Beaver Valley Power Station, Units 1 and 2. License Renewal Application (TAC Nos. MD6593 and MD6594) and License Renewal Application Amendment No. 30 L-07-038, Decommissioning Report for Year Ending December 31, 20062007-03-28028 March 2007 Decommissioning Report for Year Ending December 31, 2006 ML0610402602005-03-30030 March 2005 Decommissioning Reports for the Beaver Valley Power Station, Units 1 and 2 L-03-034, Decommissioning Reports for Beaver Valley Power Station, Units 1 & 22003-03-21021 March 2003 Decommissioning Reports for Beaver Valley Power Station, Units 1 & 2 L-02-106, License Amendment Request Nos. 299 & 1712002-10-31031 October 2002 License Amendment Request Nos. 299 & 171 L-02-067, Revised Decommissioning Funding Report for 20012002-06-0404 June 2002 Revised Decommissioning Funding Report for 2001 2023-03-31
[Table view] Category:70
MONTHYEARL-23-061, Submittal of the Decommissioning Funding Status Reports2023-03-31031 March 2023 Submittal of the Decommissioning Funding Status Reports L-21-046, Submittal of the Decommissioning Funding Status Reports for Beaver Valley Power Station, Unit Nos. 1 and 2, Davis-Besse Nuclear Power Station, and Perry Nuclear Power Plant2021-03-29029 March 2021 Submittal of the Decommissioning Funding Status Reports for Beaver Valley Power Station, Unit Nos. 1 and 2, Davis-Besse Nuclear Power Station, and Perry Nuclear Power Plant ML17114A0622017-04-24024 April 2017 Supplemental Information Regarding Decommissioning Funding Status Report L-17-028, Submittal of the Decommissioning Funding Status Reports2017-03-24024 March 2017 Submittal of the Decommissioning Funding Status Reports L-15-327, ISFSI; Davis-Besse, Unit 1 & ISFSI and Perry, Unit 1 & ISFSI - Triennial ISFSI Decommissioning Funding Plans2015-12-0909 December 2015 ISFSI; Davis-Besse, Unit 1 & ISFSI and Perry, Unit 1 & ISFSI - Triennial ISFSI Decommissioning Funding Plans L-15-101, Submittal of the Decommissioning Funding Status Reports for Beaver Valley, Units 1 and 2, Davis-Besse and Perry, Unit 12015-03-31031 March 2015 Submittal of the Decommissioning Funding Status Reports for Beaver Valley, Units 1 and 2, Davis-Besse and Perry, Unit 1 L-14-303, ISFSI, Submittal of Decommissioning Funding Plan2014-12-0808 December 2014 ISFSI, Submittal of Decommissioning Funding Plan L-11-102, Submittal of the Decommissioning Reports2011-03-29029 March 2011 Submittal of the Decommissioning Reports L-09-187, Supplemental Information for Decommissioning Funding Report2009-07-28028 July 2009 Supplemental Information for Decommissioning Funding Report L-09-064, Submittal of Decommissioning Reports for Year Ending December 31, 20082009-03-27027 March 2009 Submittal of Decommissioning Reports for Year Ending December 31, 2008 L-08-332, Supplemental Information for the Review of the Beaver Valley Power Station, Units 1 and 2. License Renewal Application (TAC Nos. MD6593 and MD6594) and License Renewal Application Amendment No. 302008-11-0505 November 2008 Supplemental Information for the Review of the Beaver Valley Power Station, Units 1 and 2. License Renewal Application (TAC Nos. MD6593 and MD6594) and License Renewal Application Amendment No. 30 L-07-038, Decommissioning Report for Year Ending December 31, 20062007-03-28028 March 2007 Decommissioning Report for Year Ending December 31, 2006 ML0610402602005-03-30030 March 2005 Decommissioning Reports for the Beaver Valley Power Station, Units 1 and 2 L-03-034, Decommissioning Reports for Beaver Valley Power Station, Units 1 & 22003-03-21021 March 2003 Decommissioning Reports for Beaver Valley Power Station, Units 1 & 2 L-02-106, License Amendment Request Nos. 299 & 1712002-10-31031 October 2002 License Amendment Request Nos. 299 & 171 L-02-067, Revised Decommissioning Funding Report for 20012002-06-0404 June 2002 Revised Decommissioning Funding Report for 2001 2023-03-31
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Text
F NOC'r Beaver Valley Power Station F______P.O. Box 4 "Shippingport, PA 15077 FirstEnergyNuclear Operating Company Kevin L. Ostrowski 724-682-5234 Director,Site Operations Fax: 724-643-8069 November 5, 2008 L-08-332 10 CFR 54 ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555-0001
SUBJECT:
Beaver Valley Power Station, Unit Nos. 1 and 2 BV-1 Docket No. 50-334, License No. DPR-66 BV-2 Docket No. 50-412, License No. NPF-73 Supplemental Information for the Review of the Beaver Valley Power Station, Units 1 and 2. License Renewal Application (TAC Nos. MD6593 and MD6594) and License Renewal Application Amendment No. 30 The Reference provided the FirstEnergy Nuclear Operating Company (FENOC) License Renewal Application (LRA) for the Beaver Valley Power Station (BVPS). During a conference call held between FENOC and the Nuclear Regulatory Commission (NRC) on October 8, 2008, the NRC requested supplemental information related to LRA Section 4.6.1.1. This letter provides the requested supplemental information and Amendment No. 30 to the LRA.
The Attachment provides the FENOC reply to the NRC request for supplemental information. The Enclosure provides Amendment No. 30 to the BVPS LRA.
There are no regulatory commitments contained in this letter. If there are any questions or if additional information is required, please contact Mr. Clifford I. Custer, Fleet License Renewal Project Manager, at 724-682-7139.
I declare under penalty of perjury that the foregoing is true and correct. Executed on November *", 2008.
Sincerely, Kevin L. Ostrowski AicQ
Beaver Valley Power Station, Unit Nos. 1 and 2 L-08-332 Page 2
Reference:
FENOC Letter L-07-113, "License Renewal Application," August 27, 2007.
Attachment:
Supplemental Information Regarding Beaver Valley Power Station, Units 1 and 2, License Renewal Application, Section 4.6.1.1
Enclosure:
Amendment No. 30 to the BVPS License Renewal Application cc: Mr. K. L. Howard, NRC DLR Project Manager Mr. S. J. Collins, NRC Region I Administrator cc: w/o Attachment or Enclosure Mr. B. E. Holian, NRC DLR Director Mr. D. L. Werkheiser, NRC Senior Resident Inspector Ms. N. S. Morgan, NRC DORL Project Manager Mr. D. J. Allard, PA BRP/DEP Director Mr. L. E. Ryan, PA BRP/DEP
ATTACHMENT L-08-332 Supplemental Information Regarding Beaver Valley Power Station, Units 1 and 2, License Renewal Application, Section 4.6.1.1 Page 1 of 2 Section 4.6.1.1 During a conference call held on October 8, 2008 between FENOC and the NRC, it was agreed that clarification or corrections would be provided to address the following:
a) Expected stresses resulting from the 60-year anticipated operating basis earthquake were determined to be bounded by those due to the analyzed design basis earthquake (DBE) cycles.
b) 10 CFR 54.21(c)(1)(ii) was used to disposition the Unit 1 Containment Liner Fatigue TLAA.
c) DBE design cycles are not provided in Table 5.2-13 of the Unit 1 UFSAR.
RESPONSE
a) Expected stresses resulting from the 60-year anticipated operating basis earthquake were determined to be bounded by those due to the analyzed design basis earthquake (DBE) cycles.
These design loads include 1000 cycles of pressure variation due to normal operations (startup and shutdown), 4000 cycles of temperature variation due to normal operations (startup and shutdown), and 20 cycles of design basis earthquake (DBE). The fatigue analysis determined the stress due to the combination of thermal, normal operating and DBE loadings. That combination was then considered as 4000 cycles of a fluctuation from the operating condition (including DBE) to the zero stress state in determining the cumulative usage factor (CUF). The 60-year anticipated occurrences of 150 pressure cycles, 600 temperature cycles and 150 operating basis earthquake (OBE) cycles are bounded by the 4000 analyzed cycles.
The LRA is amended to provide the above clarification.
b) 10 CFR 54.21(c)(1)(ii) was used to disposition the Unit I Containment Liner Fatigue TLAA.
The fatigue analysis determined the stress due to the combination of thermal, normal operating and DBE loadings. That combination was then considered as
Attachment L-08-332 Page 2 of 2 4000 cycles of a fluctuation from the operating condition (including DBE) to the zero stress state in determining the CUF. The 60-year anticipated occurrences of 150 pressure cycles, 600 temperature cycles and 150 OBE cycles are bounded by the 4000 analyzed cycles. Therefore, no revision to the Unit 1 containment liner stress analysis was required.
The LRA is amended to change the TLAA disposition from 10 CFR 54.21(c)(1)(ii) to 10 CFR 54.21(c)(1)(i).
c) DBE design cycles are not provided in Table 5.2-13 of the Unit 1 UFSAR.
The Unit 1 containment liner stress analysis determines a fatigue usage factor based on specific design cyclic loads in accordance with paragraph N-415.2 of the 1968 Edition of ASME Section II1. These design loads include 1000 cycles of pressure variation due to normal operations (startup and shutdown), 4000 cycles of temperature variation due to normal operations (startup and shutdown), and 20 cycles of DBE. As provided in Table 5.2-13 of the Unit 1 UFSAR, the stress allowables are established in accordance with ASME Ill paragraph N-415.1 or N-415.2.
In addition, the design loads of 1000 cycles of pressure variation due to normal operations (startup and shutdown), 4000 cycles of temperature variation due to normal operations (startup and shutdown), and 20 cycles of DBE are included in Appendix A, "Updated Final Safety Analysis Report Supplement," of the LRA.
No LRA change is required.
See the Enclosure to this letter for the revisions to the BVPS LRA.
ENCLOSURE Beaver Valley Power Station (BVPS), Unit Nos. 1 and 2 Letter L-08-332 Amendment No. 30 to the BVPS License Renewal Application Page 1 of 5 License Renewal Application Sections Affected Section 4.6.1.1 Section A.2.5.1 The Enclosure identifies the correction by Affected License Renewal Application (LRA)
Section, LRA Page No., and Affected Paragraph and Sentence. The count for the affected paragraph, sentence, bullet, etc. starts at the beginning of the affected Section or at the top of the affected page, as appropriate. Below each section the reason for the change is identified, and the sentence affected is printed in italics with deleted text fined-ou and added text underlined.
Enclosure L-08-332 Page 2 of 5 Affected Paragraph Affected LRA Section LRA Page No. and Sentence Section 4.6.1.1 Page 4.6-1 Entire section During a conference call held on October 8, 2008 between FirstEnergy Nuclear Operating Company (FENOC) and the U.S. Nuclear Regulatory Commission (NRC), it was agreed that clarification or corrections would be provided to Section 4.6.1.1 of the License Renewal Application (LRA) for BVPS.
Section 4.6.1.1 is replaced it its entirety to read as follows:
The Unit 1 containmentliner stress analysis determines a fatigue usage factor based on specific design cyclic loads in accordance with paragraphN-415.2 of the 1968 Edition of ASME Section III. These design loads include 1000 cycles of pressure variation due to normal operations (startup and shutdown), 4000 cycles of temperature variationdue to normal operations(startup and shutdown), and 20 cycles of desiqn basis earthquake (DBE). The fatigue analysis determined the stress due to the combination of thermal, normal operating and DBE loadings. That combination was then consideredas 4000 cycles of a fluctuation from the operating condition (includingDBE) to the zero stress state in determining the cumulative usage factor (CUF). The CUF was determined to be significantly less than 1.0.
The anticipatedoccurrencesof these cycles are described in Table 5.2-13 of the Unit I UFSAR as follows:
0 150 cycles of loading due to the differentialpressure between operating and atmospheric pressure are assumed on the basis of 2.5 refueling cycles per year on a 60-year span;
- 600 cycles of loading due to thermal expansion resulting when the liner is exposed to the differentialtemperature between operatingand seasonal refueling temperaturesare assumed on the basis of 10 such variationsper year on a 60 year span;
- 150 cycles of operatingbasis earthquake (OBE) is an assumed number of cycles of this type of earthquake for a 60 year span.
As shown above the 60-year anticipatedoccurrences of pressure cycles, temperature cycles and OBE cycles are bounded by the 4000 analyzed cycles.
Therefore, the Unit I Containment liner fatigue TLAA has been dispositioned in accordancewith 10 CFR 54.21(c)(1)(i).
Enclosure L-08-332 Page 3 of 5 The Unit 1 Containment liner stress analysi determines a fatigue usage factot based on spec~ifi design cyclic loads in accordance with paragraph N 415.2 ot the 1968 Edition of ASME- Scction Ml.These design loads include 1000 cycles o?
pressurc variation due to normal operations (starp adsutdown), -4000cycle of te eratur-e variation due to normal ope (startup and shutdown), and 20 cycles of design baisis earthquake. The usage factor-for the finer-wais determined to be sign*ifantly less han 1.h0. The antiipated Ocurrences of these cycles are described in Table 5.2 13 of the Unit I UFSAR as follow-S ytv v 15 s ie of~*# ledn v due* EdiffigVr-entV tm the ialV p *msum be hVeEnJ opvm tV and atmospheric pressure are antieipated on the basis of 2.5 refueling cycles per year on a 60 yeaF spanl
- 600 cycles of loading due to thermal expansion resulting when the liner-i exposed to the differential teemprture between operating and seasonal refueling temperatur-es arc anticiated on the basi of103uc. vritin per-year on a 60 yle-ar span; and,-
4150 cycles of operating, basis earthquake, which is an assumed number 0?
cycles of this tye of earthquake for a 60 yoear span.
As shown above, the design cycleis of the Unit I Containment liner boundth anticipated pressure and temper~ature cycles expected throu~g~h the period oe extended operation. The expected stresses resulting from thi0ya ntic-ipated to the analyzed design basis earthquake cycles. Therefore, the Unit I Cntaninment liner fatigue TLMA has been dispositoned in accordance with 10 CFR 54.24(c)(4)(4i).
. I Enclosure L-08-332 Page 4 of 5 Affected Paragraph Affected LRA Section LRA Page No. and Sentence Section A.2.5.1 Page A.2-12 Entire section During a conference call held on October 8, 2008 between FENOC and the NRC, it was agreed that clarification or corrections would be provided to Section 4.6.1.1 of the LRA for BVPS. Associated Section A.2.5.1 is replaced it its entirety to read as follows:
The Unit I containmentliner stress analysis determines a fatigue usage factor based on specific design cyclic loads in accordance with ParagraphN-415.2 of the 1968 Edition of ASME Section III. These design loads include 1000 cycles of pressure variation due to normal operations (startup and shutdown), 4000 cycles of temperature variationdue to normal operations(startup and shutdown), and 20 cycles of design basis earthquake (DBE). The fatigue analysis determined the stress due to the combination of thermal, normal operatingand DBE loadings. That combination was then consideredas 4000 cycles of a fluctuation from the operating condition (includingDBE) to the zero stress state in determining the cumulative usage factor (CUF). The CUF was determined to be significantlyless than 1.0.
The anticipatedoccurrences of these cycles are described in Table 5.2-13 of the Unit I UFSAR as follows:
- 150 cycles of loading due to the differential pressure between operating and atmospheric pressure are assumed on the basis of 2.5 refueling cycles per year on a 60-year span;
- 600 cycles of loading due to thermal expansion resulting when the liner is exposed to the differential temperature between operating and seasonal refueling temperaturesare assumed on the basis of 10 such variationsper year on a 60 year span:
0 150 cycles of operatingbasis earthquake (OBE) is an assumed number of cycles of this type of earthquake for a 60 year span.
As shown above the 60-year anticipatedoccurrences of pressure cycles, temperature cycles and OBE cycles are bounded by the 4000 analyzed cycles.
Therefore, the Unit I Containment liner fatigue TLAA has been dispositioned in accordance with 10 CFR 54.21(c)(1)(i).
Enclosure L-08-332 Page 5 of 5 The Unit I Containment liner-stress analysi determines a fAtigue usage factor based on spccifi design cGycc*loads in a-cordance with paragraph N 415.2 e" the 1968 Editon of ASME- Section WI.These design loads include 1000 cycles of pressure variation due to normal operations 6staitup and shutdown), 4000 cycles of teemprture variation due to normal operations (stadup and shutdown), an 20 cycles of design basis cafthquake. The usage factor for-the liner was determined to be significantly leiss than 1.0. The anticiated occurrences of these cycles are desribed in Table 5.2 13 of the Unit I UFSAR as fllows., I 150 cycles of loading due to the differential pressure behAw'en operating and atmospheric pressure are anticipated on the basis of 2.5 refueliny cycleis per year on a 60 year-span;
-600 cycles of leading due to thermal xpo esulting when the liner is exposed to the differential temepeaturep between operating and seasonal refueling temperatures are anticipated on the basis of 10 such variations per-year on a 60 year span; and,-
cycles of this type of eadh quake for a 60 ye-ar span.
As shown above, the design cycles of the Unit I Containment liner-boundth anticiated pressure and temgperature cycles expected throug9h the period ot extended operation. The expected stresses reisulting from thi0ya nticipated to the analyed deisign baisis eagh quake cycles. Therefor-e, the Unit I Containment liner faiue TLAA has been dispositioned in accordance with410 CFF? 54.21(c)(1)(ii).