Letter Sequence Other |
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TAC:ME4640, Steam Generator Tube Integrity (Approved, Closed) |
Results
- Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval
Other: L-11-114, Drawing No. M-042B, Rev. 35, Sampling System Sh. 2 Local Grab Samples, L-11-131, Drawing No. LR-OS041A2, Revision 1, Operational Schematic Emergency Diesel Generator Systems., L-11-334, Reply to Request Additional Information for the Review of the License Renewal Application Amendment No. 21, L-12-337, Review of the Safety Evaluation Report with Open Items Related to the License Renewal, L-12-444, Submittal of Contractor Equivalent Margins Assessments for Reactor Vessel Welds (Nonproprietary Versions), L-12-456, Notification of Closure of Commitments Related to the Review of the License Renewal Application, L-13-257, Notification of Completion of a License Renewal Commitment Related to the Review of License Renewal Application TAC No. ME4640) and License Renewal Application Amendment No. 45), L-13-330, License Renewal Application Amendment No. 46 - Annual Update, L-13-341, Review of the Safety Evaluation Report Related to the License Renewal of Davis-Besse Nuclear Power Station, L-14-085, License Renewal Application (TAC No. ME4640) Amendment No. 48, L-14-206, License Renewal Application Amendment No. 50 - Annual Update, L-15-120, Notification of Completion of License Renewal Commitments Related to the Review of the Davis-Besse Nuclear Power Station, Unit No. 1, License Renewal Application and License Renewal Application Amendment No. 55, L-15-139, License Renewal Reactor Vessel Internals Inspection Plan, L-15-214, License Renewal Application Amendment No. 59 - Annual Update, L-15-309, License Renewal Application Amendment No. 60, L-15-310, C-CSS-099.20-069, Rev 0, Shield Building Laminar Cracking Limits., ML102450565, ML111050091, ML11110A089, ML11110A091, ML11110A092, ML11110A093, ML11110A094, ML11110A095, ML11110A105, ML11110A106, ML11110A107, ML11122A014, ML11126A017, ML11126A018, ML11126A019, ML11126A020, ML11126A021, ML11126A022, ML11126A023, ML11126A024, ML11126A025, ML11126A026, ML11126A032, ML11126A033, ML11126A034, ML11126A035, ML11126A036, ML11126A037, ML11126A038, ML11126A039, ML11126A040, ML11126A041, ML11126A042, ML11126A043... further results
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MONTHYEARML11126A0882008-01-12012 January 2008 Drawing No. LR-M041B, Revision 1, Piping & Instrument Diagram Primary Service Water System. Job Code 12501 Project stage: Other ML11126A0902008-01-15015 January 2008 Drawing No. LR-OS41A1, Revision 1, Operational Schematic Emergency Diesel Generator Systems. Project stage: Other L-11-131, Drawing No. LR-OS041A2, Revision 1, Operational Schematic Emergency Diesel Generator Systems.2008-01-15015 January 2008 Drawing No. LR-OS041A2, Revision 1, Operational Schematic Emergency Diesel Generator Systems. Project stage: Other ML11126A0682008-05-0505 May 2008 Drawing No. LR-M-037E, Revision 28, Piping & Instrument Diagram Clean Liquid Radioactive Waste System. Project stage: Other ML11126A0652008-08-0606 August 2008 Drawing No. LR-M036B, Revision 1, Piping & Instrument Diagram Component Cooling Water System. Project stage: Other ML11126A0592008-10-0909 October 2008 Drawing No. LR-M033A, Revision 1, Piping & Instrument Diagram High Pressure Injection. Project stage: Other ML11126A0632008-10-10010 October 2008 Drawing No. LR-M033B, Revision 1, Piping & Instrument Diagram Decay Heat Train 1. Project stage: Other ML11126A0702008-10-10010 October 2008 Drawing No. LR-M033C, Revision 1, Piping & Instrument Diagram Decay Heat Train 2. Project stage: Other ML11126A0742008-11-0606 November 2008 Drawing No. LR-M043, Revision 1, Piping & Instrument Diagram Auxiliary Building Chilled Water System. Project stage: Other ML11126A0832008-12-18018 December 2008 Drawing No. LR-M038C, Revision 2, Piping & Instrument Diagram Gaseous Radioactive Waste System. Job Code 12501 Project stage: Other ML11126A0712009-04-0707 April 2009 Drawing No. LR-M034, Revision 1, Piping & Instrument Diagram Emerg. Core Cooling System Ctmt. Spray & Core Flooding Systems. Project stage: Other ML11126A0892009-04-0707 April 2009 Drawing No. LR-OS002, Revision 1, Operational Schematic Makeup and Purification System. Project stage: Other ML1024505652010-08-27027 August 2010 License Renewal Application and Ohio Coastal Management Program Consistency Certification Project stage: Other ML1104500462011-02-17017 February 2011 Request for Additional Information for the Review of the Davis-Besse Nuclear Power Station - Fire Protection Project stage: RAI ML11126A0792011-02-25025 February 2011 Drawing No. LR-M900A, Revision 0, Instrument Air System Piping Schematic. Project stage: Other ML1104205972011-02-28028 February 2011 Request for Additional Information for the Review of the Davis-Besse Nuclear Power Station - Section 2.4 Project stage: RAI ML1106801722011-03-17017 March 2011 Request for Additional Information on the Reactor Vessel Surveillance Aging Management Program, Time-Limited Aging Analyses for Neutron Embrittlement of the Rv and Internals, and Other TLAAs for the Review of the Davis-Besse Nuclear Power S Project stage: RAI ML1107007322011-03-18018 March 2011 Request for Additional Information for the Review of the Davis-Besse Nuclear Power Station-Section 2.2 & 2.3 Project stage: RAI L-11-078, Reply to Request for Additional Information for the Review of License Renewal Application (TAC ME4640) Amendment No. 12011-03-18018 March 2011 Reply to Request for Additional Information for the Review of License Renewal Application (TAC ME4640) Amendment No. 1 Project stage: Response to RAI ML11068A0002011-03-21021 March 2011 Request for Additional Information for the Review of the Davis-Besse Nuclear Power Station - Section 4.7 (TAC Number ME4640) Project stage: RAI L-11-079, Reply to Request for Additional Information for the Review of the License Renewal Application2011-03-23023 March 2011 Reply to Request for Additional Information for the Review of the License Renewal Application Project stage: Response to RAI L-11-089, Reply to Request for Additional Information for the Review License Renewal Application2011-03-23023 March 2011 Reply to Request for Additional Information for the Review License Renewal Application Project stage: Response to RAI ML1108206242011-03-30030 March 2011 Request for Additional Information for the Review of the Davis-Besse Nuclear Power Station-Section 2.1 (Tac No. ME4640) Project stage: RAI ML1109002952011-03-31031 March 2011 Safety Evaluation Report Related to the License Renewal of Salem Nuclear Generating Station Project stage: Approval ML1108204902011-04-0505 April 2011 Request for Additional Information for the Review of the Davis-Besse Nuclear Power Station - Batch 1 Project stage: RAI ML11110A0932011-04-15015 April 2011 Drawing No. M-037D, Rev. 21, Clean Liquid Radioactive Waste System Project stage: Other ML11110A1072011-04-15015 April 2011 Drawing No. M-045, Rev. 56, Chemical Addition Systems Project stage: Other ML11110A1062011-04-15015 April 2011 Drawing No. M-042C, Rev. 33, Sampling System Sh. 3 Project stage: Other ML11110A1052011-04-15015 April 2011 Drawing No. M-040A, Rev. 76, Reactor Coolant System Details Project stage: Other ML11110A0952011-04-15015 April 2011 Drawing No. M-039B, Rev. 18, Miscellaneous Liquid Radioactive Waste Project stage: Other ML11110A0942011-04-15015 April 2011 Drawing No. M-039A, Rev. 33, Miscellaneous Liquid Radioactive Waste Project stage: Other ML11110A0922011-04-15015 April 2011 Drawing No. M-037C, Rev. 30, Clean Liquid Radioactive Waste System Project stage: Other L-11-114, Drawing No. M-042B, Rev. 35, Sampling System Sh. 2 Local Grab Samples2011-04-15015 April 2011 Drawing No. M-042B, Rev. 35, Sampling System Sh. 2 Local Grab Samples Project stage: Other L-11-107, Reply to Request for Additional Information on Reactor Vessel Surveillance Aging Management Program & Time-Limited Aging Analyses for Neutron Embrittlement for Review of License Renewal Application & License Renewal Application...2011-04-15015 April 2011 Reply to Request for Additional Information on Reactor Vessel Surveillance Aging Management Program & Time-Limited Aging Analyses for Neutron Embrittlement for Review of License Renewal Application & License Renewal Application... Project stage: Response to RAI ML11110A0882011-04-15015 April 2011 Reply to Request for Additional Information for the Review of the License Renewal Application, Sections 2.2 & 2.3, License Renewal Application Amendment No. 3, and Revised License Renewal Project stage: Response to RAI ML11110A0912011-04-15015 April 2011 Drawing No. M-011, Rev. 61, Domestic Water System Project stage: Other ML11110A0892011-04-15015 April 2011 Drawing No. M-0060, Rev. 52, Auxiliary Feedwater System Project stage: Other ML1110500912011-04-19019 April 2011 Scoping and Screening Audit Report Regarding the Davis-Besse Nuclear Power Station License Renewal Application Project stage: Other L-11-115, Reply to Request for Additional Information for the Review of the License Renewal Application and License Renewal Application Amendment No. 42011-04-20020 April 2011 Reply to Request for Additional Information for the Review of the License Renewal Application and License Renewal Application Amendment No. 4 Project stage: Response to RAI ML1109807182011-04-20020 April 2011 Request for Additional Information for the Review of the Davis-Bessie Nuclear Power Station - Batch 2 Project stage: RAI ML11126A0362011-04-29029 April 2011 Drawing No. LR-M017D, Revision 1 Piping & Instrument Diagram, Steam Blackout Diesel Generator. Project stage: Other ML11126A0352011-04-29029 April 2011 Drawing No. LR-M017C, Revision 2, Piping & Instrument Diagram, Fuel Oil. Project stage: Other ML11126A0342011-04-29029 April 2011 Drawing No. LR-M017B, Revision 1, Piping & Instrument Diagram, Diesel Generators Air Start. Project stage: Other ML11126A0332011-04-29029 April 2011 Drawing No. LR-M016B, Revision 1, Piping & Instrument Diagram Station Fire Protection System Project stage: Other ML11126A0322011-04-29029 April 2011 Drawing No. LR-M016A, Revision 1, Piping & Instrument Diagram Station Fire Protection System Project stage: Other ML11126A0262011-04-29029 April 2011 Drawing No. LR-M010C, Revision 1, Piping & Instrument Diagram Make-up Water Treatment System Project stage: Other ML11126A0252011-04-29029 April 2011 Drawing No. LR-M010A, Revision 1, Piping & Instrument Diagram Make-Up Water Treatment System Project stage: Other ML11126A0242011-04-29029 April 2011 Drawing No. LR-M009B, Revision 1, Piping & Instrument Diagram Cooling Water System Project stage: Other ML11126A0192011-04-29029 April 2011 Drawing No. LR-M003A, Revision 1, Piping & Instrument Diagram Main Steam and Reheat System. Sheet 1 Project stage: Other ML11126A0452011-04-29029 April 2011 Drawing No. LR-M024H, Revision 1, Piping & Instrument Diagram, No. 2 Main and Auxiliary Turbine Driven Feed Pumps. Project stage: Other 2011-02-25
[Table View] |
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Category:Letter
MONTHYEARL-24-233, Proposed Alternative Request to Defer ASME Code Section XI Inservice Inspection Examinations for Pressurizer and Steam Generator Pressure-Retaining Welds and Full Penetration Welded Nozzles2024-12-18018 December 2024 Proposed Alternative Request to Defer ASME Code Section XI Inservice Inspection Examinations for Pressurizer and Steam Generator Pressure-Retaining Welds and Full Penetration Welded Nozzles L-24-259, ISFSI; Davis-Besse Nuclear Power Station, Unit No. 1 ISFSI & Perry Nuclear Power Plant, Unit No. 1 ISFSI - Triennial ISFSI Decommissioning Funding Plan2024-12-17017 December 2024 ISFSI; Davis-Besse Nuclear Power Station, Unit No. 1 ISFSI & Perry Nuclear Power Plant, Unit No. 1 ISFSI - Triennial ISFSI Decommissioning Funding Plan 05000346/LER-2021-001-02, Emergency Diesel Generator Speed Switch Failure Due to Direct Current System Ground2024-12-0909 December 2024 Emergency Diesel Generator Speed Switch Failure Due to Direct Current System Ground IR 05000346/20240102024-12-0606 December 2024 Comprehensive Engineering Team Inspection Report 05000346/2024010 L-24-227, Response to Request for Additional Information for Relief Request RR-A 12024-11-20020 November 2024 Response to Request for Additional Information for Relief Request RR-A 1 IR 05000346/20244022024-11-19019 November 2024 Material Control and Accounting Program Inspection Report 05000346/2024402 (Public) IR 05000346/20240032024-11-14014 November 2024 Integrated Inspection Report 05000346/2024003 ML24303A3282024-10-29029 October 2024 Information Request for the Cyber Security Baseline Inspection Identification to Perform Inspection ML24281A0662024-10-0404 October 2024 EN 57363 - MPR Associates, Inc. Report in Accordance with 10 CFR Part 21 on Incomplete Dedication of Contactors Supplied as Basic Components IR 05000346/20244032024-09-27027 September 2024 Security Baseline Inspection Report 05000346/2024403 ML24269A0552024-09-25025 September 2024 Submittal of the Updated Final Safety Analysis Report, Revision 35 05000346/LER-2021-001-01, Emergency Diesel Generator Speed Switch Failure Due to Direct Current System Ground2024-09-19019 September 2024 Emergency Diesel Generator Speed Switch Failure Due to Direct Current System Ground 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 ML24260A2382024-09-16016 September 2024 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information ML24255A8032024-09-11011 September 2024 Technical Specification 5.6.6 Steam Generator Tube Inspection 180-Day Report ML24255A8642024-09-0606 September 2024 Rscc Wire & Cable LLC Dba Marmon Industrial Energy & Infrastructure - Part 21 Retraction of Final Notification ML24249A1602024-09-0505 September 2024 Information Request to Support Upcoming Material Control and Accounting Inspection at Davis-Besse Nuclear Power Station L-24-188, Submittal of Quality Assurance Program Manual, Revision 302024-08-27027 August 2024 Submittal of Quality Assurance Program Manual, Revision 30 ML24239A3972024-08-23023 August 2024 Rssc Wire & Cable LLC Dba Marmon - Part 21 Final Notification - 57243-EN 57243 IR 05000346/20240052024-08-22022 August 2024 Updated Inspection Plan for Davis-Besse Nuclear Power Station (Report 05000346/2024005) 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 05000346/20240022024-08-0101 August 2024 Integrated Inspection Report 05000346/2024002 IR 05000346/20244012024-07-30030 July 2024 Security Baseline Inspection Report 05000346/2024401 ML24208A0962024-07-25025 July 2024 57243-EN 57243 - Rssc Wire & Cable LLC, Dba Marmon - Part 21 Notification L-24-032, Cycle 23 and Refueling Outage 23 Inservice Inspection Summary Report2024-07-15015 July 2024 Cycle 23 and Refueling Outage 23 Inservice Inspection Summary Report L-24-063, License Amendment Request to Remove the Table of Contents from the Technical Specifications2024-07-0808 July 2024 License Amendment Request to Remove the Table of Contents from the Technical Specifications L-24-024, Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2024-06-19019 June 2024 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models L-23-214, Submittal of Relief Request for Impractical American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI Examination Requirements2024-06-0505 June 2024 Submittal of Relief Request for Impractical American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI Examination Requirements L-24-019, Unit No.1 - Report of Facility Changes, Tests, and Experiments2024-05-22022 May 2024 Unit No.1 - Report of Facility Changes, Tests, and Experiments ML24142A3532024-05-21021 May 2024 Station—Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection L-24-111, Response to Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-05-15015 May 2024 Response to Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations L-24-072, Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report - 20232024-05-15015 May 2024 Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report - 2023 L-24-031, Unit No.1 - Steam Generator Tube Circumferential Crack Report - Spring 2024 Refueling Outage2024-05-14014 May 2024 Unit No.1 - Steam Generator Tube Circumferential Crack Report - Spring 2024 Refueling Outage IR 05000346/20240012024-05-0303 May 2024 Integrated Inspection Report 05000346/2024001 L-24-069, Occupational Radiation Exposure Report for Year 20232024-04-30030 April 2024 Occupational Radiation Exposure Report for Year 2023 L-24-018, Submittal of Core Operating Limits Report, Cycle 24, Revision 02024-04-16016 April 2024 Submittal of Core Operating Limits Report, Cycle 24, Revision 0 ML24089A2582024-04-0101 April 2024 Request for Information for the NRC Quuadrennial Comprehensive Engineering Team Inspection: Inspection Report 05000346/2024010 L-24-013, Annual Notification of Property Insurance Coverage2024-03-26026 March 2024 Annual Notification of Property Insurance Coverage ML24036A3472024-03-0707 March 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0076 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML24057A0752024-03-0101 March 2024 The Associated Independent Spent Fuel Storage Installations IR 05000346/20230062024-02-28028 February 2024 Re-Issue Annual Assessment Letter for Davis-Besse Nuclear Power Station (Report 05000346/2023006) ML24057A3362024-02-28028 February 2024 Annual Assessment Letter for Davis-Besse Nuclear Power Station (Report 05000346/2023006) 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 IR 05000346/20243012024-02-0202 February 2024 NRC Initial License Examination Report 05000346/2024301 IR 05000346/20230042024-01-31031 January 2024 Integrated Inspection Report 05000346/2023004 ML23313A1352024-01-17017 January 2024 Authorization and Safety Evaluation for Alternative Request RP 5 for the Fifth 10 Year Interval Inservice Testing Program ML23353A1192023-12-19019 December 2023 Operator Licensing Examination Approval Davis Besse Nuclear Power Station, January 2024 L-23-260, Corrections to the 2022 Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report for the Davis-Besse Nuclear Power Station2023-12-0707 December 2023 Corrections to the 2022 Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report for the Davis-Besse Nuclear Power Station 2024-09-06
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARL-24-063, License Amendment Request to Remove the Table of Contents from the Technical Specifications2024-07-0808 July 2024 License Amendment Request to Remove the Table of Contents from the Technical Specifications 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 CP-202300157, ISFSI, Beaver Valley, Units 1 and 2, ISFSI, Davis-Besse, Unit 1, ISFSI, Perry, Unit 1, and ISFSI, Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-04-14014 April 2023 ISFSI, Beaver Valley, Units 1 and 2, ISFSI, Davis-Besse, Unit 1, ISFSI, Perry, Unit 1, and ISFSI, Application for Order Consenting to Transfer of Licenses and Conforming License Amendments ML22277A6012022-10-14014 October 2022 Issuance of Amendment No. 304 Revising the Design Basis for the Shield Building Containment Structure L-20-163, License Amendment Request to Incorporate the Applicable Standard Technical Specification 5.2.2, Unit Staff, Into the Facility Technical Specifications2020-07-27027 July 2020 License Amendment Request to Incorporate the Applicable Standard Technical Specification 5.2.2, Unit Staff, Into the Facility Technical Specifications L-20-188, ISFSI, Davis-Besse Unit 1, and ISFSI, Perry, Unit 1, and ISFSI, Decommissioning Trust: Amendments to Decommissioning Trust Agreements to Update Company Names2020-06-26026 June 2020 ISFSI, Davis-Besse Unit 1, and ISFSI, Perry, Unit 1, and ISFSI, Decommissioning Trust: Amendments to Decommissioning Trust Agreements to Update Company Names L-19-233, License Amendment Request for Adoption of TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control - Risk Informed Technical Specification Task Force (RITSTF) Initiative 5b2019-11-14014 November 2019 License Amendment Request for Adoption of TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control - Risk Informed Technical Specification Task Force (RITSTF) Initiative 5b L-19-219, Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2019-09-25025 September 2019 Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments L-19-200, ISFSI, Davis-Besse, Unit 1, ISFSI, Perry, Unit 1, ISFSI - Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2019-08-29029 August 2019 ISFSI, Davis-Besse, Unit 1, ISFSI, Perry, Unit 1, ISFSI - Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments ML19241A2432019-08-26026 August 2019 License Amendment Request to Extend Containment Leakage Test Interval ML19130A1952019-05-0808 May 2019 Letter - FEMA Review of Proposed Changes to DBNPS Emergency Plan for Permanently Defueled Condition L-19-073, ISFSI, Davis-Besse, Unit 1, ISFSI, and Perry, Unit 1, ISFSI - Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2019-04-26026 April 2019 ISFSI, Davis-Besse, Unit 1, ISFSI, and Perry, Unit 1, ISFSI - Application for Order Consenting to Transfer of Licenses and Conforming License Amendments L-19-062, Supplement to License Amendment Request - Proposed Changes to Technical Specifications Sections 1.1. Definitions, 5.0., Administrative Controls. for Permanently Defueled Condition2019-02-27027 February 2019 Supplement to License Amendment Request - Proposed Changes to Technical Specifications Sections 1.1. Definitions, 5.0., Administrative Controls. for Permanently Defueled Condition L-18-271, License Amendment Request - Proposed Post-Shutdown Emergency Plan2019-02-0505 February 2019 License Amendment Request - Proposed Post-Shutdown Emergency Plan L-18-242, License Amendment Request - Proposed License and Associated Technical Specification Changes for Permanently Defueled Condition2019-02-0505 February 2019 License Amendment Request - Proposed License and Associated Technical Specification Changes for Permanently Defueled Condition L-18-249, Supplemental Information Regarding License Amendment Request to Adopt National Fire Protection Association (NFPA) Standard 8052018-11-20020 November 2018 Supplemental Information Regarding License Amendment Request to Adopt National Fire Protection Association (NFPA) Standard 805 L-18-254, License Amendment Request - Proposed Changes to Technical Specifications Sections 1.1, Definitions, and 5.0, Administrative Controls, for Permanently Defueled Condition2018-10-22022 October 2018 License Amendment Request - Proposed Changes to Technical Specifications Sections 1.1, Definitions, and 5.0, Administrative Controls, for Permanently Defueled Condition L-18-203, Supplemental Information Regarding a Pending Administrative License Amendment Request to Reflect a Change in the Entity Providing a $400 Million Support Agreement2018-08-23023 August 2018 Supplemental Information Regarding a Pending Administrative License Amendment Request to Reflect a Change in the Entity Providing a $400 Million Support Agreement L-17-159, Administrative License Amendment Request to Reflect a Change in the Entity Providing a $400 Million Support Agreement2017-05-18018 May 2017 Administrative License Amendment Request to Reflect a Change in the Entity Providing a $400 Million Support Agreement L-17-026, Regarding MRP-227-A Applicant Action Item 8: Time-Limited Aging Analysis (TLAA) Regarding Reactor Vessel Internals Loss of Ductility at 60 Years2017-01-23023 January 2017 Regarding MRP-227-A Applicant Action Item 8: Time-Limited Aging Analysis (TLAA) Regarding Reactor Vessel Internals Loss of Ductility at 60 Years L-16-304, Supplement to Request for License Amendment Approval Delay2016-10-25025 October 2016 Supplement to Request for License Amendment Approval Delay L-16-020, Request for Licensing Action to Revise the Emergency Plan2016-02-17017 February 2016 Request for Licensing Action to Revise the Emergency Plan L-16-030, Request for an Amendment to Revise Technical Specification 5.5.3, Radioactive Effluents Controls Program.2016-02-0909 February 2016 Request for an Amendment to Revise Technical Specification 5.5.3, Radioactive Effluents Controls Program. L-15-341, License Amendment Request to Modify Technical Specifications 5.3.12015-11-19019 November 2015 License Amendment Request to Modify Technical Specifications 5.3.1 L-15-309, License Renewal Application Amendment No. 602015-10-0606 October 2015 License Renewal Application Amendment No. 60 L-15-214, License Renewal Application Amendment No. 59 - Annual Update2015-06-29029 June 2015 License Renewal Application Amendment No. 59 - Annual Update L-15-192, Supplemental Information for the Review of the License Renewal Application (TAC No. ME4640) and License Renewal Application Amendment No. 582015-06-12012 June 2015 Supplemental Information for the Review of the License Renewal Application (TAC No. ME4640) and License Renewal Application Amendment No. 58 L-15-166, Supplemental Information for the Review of the Davis-Besse Nuclear Power Station, Unit No. 1, Reactor Vessel Internals Inspection Plan (TAC No. ME4640) and License Renewal Application Amendment No. 562015-05-20020 May 2015 Supplemental Information for the Review of the Davis-Besse Nuclear Power Station, Unit No. 1, Reactor Vessel Internals Inspection Plan (TAC No. ME4640) and License Renewal Application Amendment No. 56 L-15-120, Notification of Completion of License Renewal Commitments Related to the Review of the Davis-Besse Nuclear Power Station, Unit No. 1, License Renewal Application and License Renewal Application Amendment No. 552015-04-0808 April 2015 Notification of Completion of License Renewal Commitments Related to the Review of the Davis-Besse Nuclear Power Station, Unit No. 1, License Renewal Application and License Renewal Application Amendment No. 55 L-15-117, License Amendment Request to Revise Emergency Diesel Generator Minimum Voltage and Frequency Surveillance Requirements2015-04-0101 April 2015 License Amendment Request to Revise Emergency Diesel Generator Minimum Voltage and Frequency Surveillance Requirements L-14-407, Request to Amend Technical Specification 5.5.15, Containment Leakage Rate Testing Program2014-12-19019 December 2014 Request to Amend Technical Specification 5.5.15, Containment Leakage Rate Testing Program L-14-297, Reply to Request for Additional Information for the Review of the Davis-Besse Nuclear Power Station, Unit No. 1, License Renewal Application (TAC No. ME4640) and License Renewal Application Amendment No. 532014-09-16016 September 2014 Reply to Request for Additional Information for the Review of the Davis-Besse Nuclear Power Station, Unit No. 1, License Renewal Application (TAC No. ME4640) and License Renewal Application Amendment No. 53 L-14-206, License Renewal Application Amendment No. 50 - Annual Update2014-06-23023 June 2014 License Renewal Application Amendment No. 50 - Annual Update L-14-085, License Renewal Application (TAC No. ME4640) Amendment No. 482014-02-19019 February 2014 License Renewal Application (TAC No. ME4640) Amendment No. 48 L-13-330, License Renewal Application Amendment No. 46 - Annual Update2013-09-20020 September 2013 License Renewal Application Amendment No. 46 - Annual Update L-12-397, Request to Amend the Price-Anderson Indemnities and Notification of a Name Change to Documents of Regulatory Interest2013-02-19019 February 2013 Request to Amend the Price-Anderson Indemnities and Notification of a Name Change to Documents of Regulatory Interest L-13-040, License Amendment Request for Proposed Revision of Technical Specification (TS) 3.4.17, Steam Generator (SG) Tube Integrity; TS 3.7.18, Steam Generator Level; TS 5.5.8, Steam Generator Program; and TS 5.6.6..2013-01-18018 January 2013 License Amendment Request for Proposed Revision of Technical Specification (TS) 3.4.17, Steam Generator (SG) Tube Integrity; TS 3.7.18, Steam Generator Level; TS 5.5.8, Steam Generator Program; and TS 5.6.6.. ML12229A1392012-08-0909 August 2012 License Renewal Application Amendment 30 - Annual Update L-12-070, License Amendment Request to Revise Emergency Diesel Generator Minimum Voltage Surveillance Requirements, and Add Figure Axis Labels2012-05-23023 May 2012 License Amendment Request to Revise Emergency Diesel Generator Minimum Voltage Surveillance Requirements, and Add Figure Axis Labels ML1126402462011-09-20020 September 2011 License Amendment Request to Change the Name of an Owner Licensee to Firstenergy Nuclear Generation, LLC L-11-097, License Amendment Request to Modify the Special Visual Inspection Requirements of Technical Specification 5.5.8, Steam Generator (SG) Program.2011-05-20020 May 2011 License Amendment Request to Modify the Special Visual Inspection Requirements of Technical Specification 5.5.8, Steam Generator (SG) Program. ML1024505632010-08-31031 August 2010 Enclosures to Davis-Besse, Unit 1, Letter L-10-221, License Renewal Application, Section 3.5 Through Appendix E, References 2.3-1 L-10-221, Enclosures to Davis-Besse, Unit 1, Letter L-10-221, License Renewal Application, Appendix E, Section 2.4 Through References E.112010-08-31031 August 2010 Enclosures to Davis-Besse, Unit 1, Letter L-10-221, License Renewal Application, Appendix E, Section 2.4 Through References E.11 L-09-143, License Amendment Request to Exclude Source Range Neutron Flux Instrument Channel Preamplifier from Channel Calibration Requirements of Technical Specification 3.3.9, Source Range Neutron Flux, & TS 3.9.2, Nuclear Instrumentation.2009-06-0202 June 2009 License Amendment Request to Exclude Source Range Neutron Flux Instrument Channel Preamplifier from Channel Calibration Requirements of Technical Specification 3.3.9, Source Range Neutron Flux, & TS 3.9.2, Nuclear Instrumentation. L-09-072, License Amendment Request to Incorporate the Use of Alternate Methodologies for Development of Reactor Pressure Vessel Pressure-Temperature Limit Curves and Request for Exemption from Certain Requirements Contained in 10 Cfr.2009-04-15015 April 2009 License Amendment Request to Incorporate the Use of Alternate Methodologies for Development of Reactor Pressure Vessel Pressure-Temperature Limit Curves and Request for Exemption from Certain Requirements Contained in 10 Cfr. L-09-025, ISFSI, and Perry, Application for Technical Specification (TS) Change for Adoption of TSTF-511 Revision 0, Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26.2009-03-25025 March 2009 ISFSI, and Perry, Application for Technical Specification (TS) Change for Adoption of TSTF-511 Revision 0, Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26. L-08-159, Supplement to License Amendment Request: Conversion of Current Technical Specifications (CTS) to Improved Technical Specifications (ITS) - Volumes 5, 6, 7, 9, 11, and 15, TAC No. MD63982008-05-16016 May 2008 Supplement to License Amendment Request: Conversion of Current Technical Specifications (CTS) to Improved Technical Specifications (ITS) - Volumes 5, 6, 7, 9, 11, and 15, TAC No. MD6398 ML0814804712008-05-16016 May 2008 Improved Technical Specification Conversion License Amendment Request, Volume 15, (Revision 1), Chapter 4.0 - Design Features ML0814804692008-05-16016 May 2008 Improved Technical Specification Conversion License Amendment Request, Volume 11, (Revision 1), Section 3.6 - Containment Systems ML0814804682008-05-16016 May 2008 Improved Technical Specification Conversion License Amendment Request, Volume 9, (Revision 1), Section 3.4 - Reactor Coolant System (RCS) 2024-07-08
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FENOC FirstEnergy Nuclear Operating Company 5501 North State Route 2 Oak Harbor. Ohio 43449 Barry S. Allen Vice President
-Nuclear 419-321-7676 Fax: 419-321-7582 August 9, 2012 L-1 2-262 10 CFR 54 ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555-0001
SUBJECT:
Davis-Besse Nuclear Power Station, Unit No. 1 Docket No. 50-346, License Number NPF-3 License Renewal Application Amendment No. 30 -Annual Update (TAC No. ME4640)By letter dated August 27, 2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML102450565), FirstEnergy Nuclear Operating Company (FENOC) submitted an application pursuant to Title 10 of the Code of Federal Regulations, Part 54 for renewal of Operating License NPF-3 for the Davis-Besse Nuclear Power Station, Unit No. 1 (Davis-Besse).
Each year following submittal of a license renewal application (LRA) and at least 3 months before scheduled completion of the NRC review, 10 CFR 54.21(b) requires an amendment to the renewal application to be submitted identifying any change to the current licensing basis (CLB) of the facility that materially affects the contents of the license renewal application, including the Final Safety Analysis Report (FSAR) supplement.
The Attachment provides a summary of the CLB changes that materially affect the LRA.Enclosure A provides Amendment No. 30 (Annual Update) to the DBNPS LRA as required by 10 CFR 54.21(b).
Enclosure B provides new and revised LRA boundary drawings.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 August __, 2012.Sincerely, Barry S. Allený' / ()5 K19 X F--F-Davis-Besse Nuclear Power Station, Unit No. 1 L-12-262 Page 2
Attachment:
Current Licensing Basis (CLB) Changes that Materially Affect the Davis-Besse Nuclear Power Station, Unit No. 1 (Davis-Besse), License Renewal Application (LRA)
Enclosures:
A. Amendment No. 30 (Annual Update) to the Davis-Besse License Renewal Application B. New and Revised Davis-Besse License Renewal Application Boundary Drawings cc: NRC DLR Project Manager NRC Region III Administrator cc: w/o Attachment or Enclosures NRC DLR Director NRR DORL Project Manager NRC Resident Inspector Utility Radiological Safety Board Attachment L-12-262 Current Licensing Basis (CLB) Changes that Materially Affect the Davis-Besse Nuclear Power Station, Unit No. 1 (Davis-Besse), License Renewal Application (LRA), Page 1 of 1 A review of Davis-Besse CLB document changes since submittal of the 2011 License Renewal Application Annual Update provided by FENOC letter dated September 30, 2011 (ML1 1276A078), identified two design changes that materially affect the contents of the Davis-Besse License Renewal Application, as follows: 1 .The Chemical Addition System was modified in March of 2012 to install a zinc injection skid. The components of the zinc injection skid satisfy the scoping criteria of 10 CFR 54.4(a)(2), and are highlighted on new license renewal boundary drawing LR-M045, Sheet 1. The aging management review results for the zinc injection skid are included in LRA Table 3.3.2-5, "Aging Management Review Results -Chemical Addition System." LRA Section 2.3.3.5, "Chemical Addition System," Table 2.3.3-5, "Chemical Addition System Components Subject to Aging Management Review," Section 3.3.2.1.5, "Chemical Addition System," and Table 3.3.2-5, "Aging Management Review Results -Chemical Addition System," are revised to account for the addition of the zinc injection skid. New license renewal boundary drawing LR-M045, Sheet 1 is added to depict the evaluation boundary of the zinc injection skid. Plant modifications associated with the addition of the zinc injection skid also resulted in changes to license renewal boundary drawings LR-MO10D Sheet 1, LR-M031A, LR-M037D and LR-M045.2. An articulating boom crane, known as the Containment Auxiliary Crane, was installed as permanent plant equipment during the Cycle 17 refueling outage that ended on June 13, 2012. This crane is capable of handling heavy loads, and therefore is subject to the requirements set forth in NUREG-0612, "Control of Lifting and Handling of Heavy Loads." The license renewal "Cranes and Hoists Inspection Program" is credited with managing the aging effects applicable to the crane structural components.
LRA Sections A. 1.10 and B.2.10, both titled "Cranes and Hoists Inspection Program," and Section A. 1.44, "References," are revised to include reference to American National Standards Institute (ANSI) B30.22, "Articulating Boom Cranes." See Enclosure A to this letter for the revision to the Davis-Besse LRA.See Enclosure B to this letter for the new and revised LRA Boundary Drawings.
Enclosure A Davis-Besse Nuclear Power Station, Unit No. 1 (Davis-Besse)
Letter L-1 2-262 Amendment No. 30 (Annual Update) to the Davis-Besse License Renewal Application Page 1 of 10 License Renewal Application Sections Affected Section 2.3.3.5 Table 2.3.3-5 Section 3.3.2.1.5 Table 3.3.2-5 Section A. 1.10 Section A. 1.44 Section B.2.10 The Enclosure identifies the change to the License Renewal Application (LRA) by Affected 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-e and added text underlined.
Enclosure A L-12-262 Page 2 of 10 Affected LRA Section LRA Page No. Affected Paragraph and Sentence 2.3.3.5 Pages 2.3-62 Description, 2 nd paragraph and new and 2.3-63 5 th paragraph; License Renewal Drawings, new drawing; and, Components Subject to AMR, 3 rd paragraph, bulleted item Based on the installation of the new Zinc Injection System, the 2 nd paragraph is revised and a new 5 th paragraph is added to the "Description" of LRA Section 2.3.3.5, "Chemical Addition System." Additionally, a new license renewal boundary drawing number is added to the list of "License Renewal Drawings," and the bulleted item under the 3 rd paragraph of "Components Subject to AMR," is revised. LRA Section 2.3.3.5 is revised to read as follows: 2 nd Paragraph revision: The Chemical Addition System provides a boric acid solution to the Boric Acid Addition System, and provides lithium hydroxide, hydrazine, ammonia, and other chemical amines to control pH and oxygen in the plant systems fed by the Reactor Coolant Chemical Addition System and Steam Generator Wet Layup Chemical Addition System. In addition, the Chemical Addition System injects zinc acetate into the RCS to reduce the radiation source term and for mitigation of primary water stress corrosion cracking (PWSCC) of Alloy 600 components.
New 5 th Paragraph:
Zinc acetate is mixed into the Zinc Iniection Mix Tank (DB-T99) with a mixer.Demineralized water is supplied from the Demineralized Water System. The solution is transferred from the Zinc Injection Mix Tank by one of two Zinc Injection Pumps (DB-P295-1 and DB-P295-2) that are capable of independent operation.
The Chemical Addition System injects zinc acetate into the RCS to reduce the radiation source term and for mitigation of primary water stress corrosion crackina (PWSCC) of Alloy 600 components Enclosure A L-12-262 Page 3 of 10 License Renewal Drawings The following license renewal drawings depict the evaluation boundaries for the system components within the scope of license renewal: LR-M035, LR-M037D, LR-M039A, LR-M039B, LR-M045, LR-M045 Sheet I Components Subject to AMR In addition to those components specifically excluded in 10 CFR 54.21(a)(1)(i), such as instruments, the following components are within the scope of license renewal but are not subject to AMR: The internals (screens) for the lithium hydroxide mix tank discharge strainer (DB-S334), the and-hydrazine pump suction strainer (DB-S335).
the zinc iniection pumps suction strainer (DB-S463) and the zinc injection pumps discharge strainer (DB-S464) are not subject to AMR because these strainers are in scope only for potential leakage and spray considerations in accordance with 10 CFR 54.4(a) (2), and serve only a structural integrity function.
Enclosure A L-12-262 Page 4 of 10 Affected LRA Section LRA Page No.Page 2.3-64 Affected Paragraph and Sentence Table 2.3.3-5 3 new rows Based on the installation of the new Zinc Injection System, LRA Table 2.3.3-5,"Chemical Addition System Components Subject to Aging Management Review," is revised to include 3 new rows, to read as follows: Component Type Intended Function ST(as defined in Table 2.0-1)Pump Casinq -Zinc iniection pumps Structural integrity (DB-P295-1
& 2)Sight glass Structural integrity Tank -Zinc iniection mix tank (DB-T99) Structural integrity Enclosure A L-12-262 Page 5 of 10 Affected LRA Section LRA Page No.Affected Paragraph and Sentence"Materials" subsection, new material;3.3.2.1.5 Page 3.3-9 Based on the installation of the new Zinc Injection System, the "Materials" subsection of Section 3.3.2.1.5, "Chemical Addition System," is revised to read as follows: Materials The materials of construction for subject mechanical components of the Chemical Addition System are: 0 Glass 0 Stainless steel Enclosure A L-12-262 Page 6 of 10 Affected LRA Section LRA Page No.Page 3.3-230 Affected Paragraph and Sentence Table 3.3.2-5 12 New Rows Based on the installation of the new Zinc Injection System, LRA Table 3.3.2-5, "Aging Management Review Results -Chemical Addition System," is revised to include 12 new rows as follows: Table 3.3.2-5 Aging Management Review Results -Chemical Addition System dAging Effect NUREG-Row Component Intended Material Environment Requiring Aging Management 1801, Table Notes No. Type Function(s)
Management Program Volume 2 Item Item Pump Casing Air with-Zinc Air w ath Iniection Structural Stainless borated water None None VII.J-16 3.3.1-99 A Pump (DB- integritx Steel leakal)ge P295-1 & 2) (External)
Pump Casing-inc Structural Stainless Air-indoor Injection Structu Stanle uncontrolled None None VII.J-15 3.3.1-94 A Pump (DB- i Steel (External)
P295-1 & 2)Pump Casing-Zinc Injection Structural Stainless Treated water Loss of Pump (DB- integrity Steel (Internal) material One-Time Insection VII.E3-15 3.3.1-24 A P295-1 & 2)
Enclosure A L-12-262 Page 7 of 10 Table 3.3.2-5 Aging Management Review Results -Chemical Addition System dAging Effect NUREG-Row Component Intended Material Environment Requiring Aging Management 1801, Table 1 Notes No. Type Function(s)
Management Program Volume 2 Item Item Pump Casing-Zinc Structural Stainless Treated water Loss of PWR Water-- Injection VIIE315 3.31-4_Pump (DB- integrit Steel (Internal) material Chemistry V. E3-15 3.3.1-24 A P295-1 & 2)Sight qlass Structural Glass Moist air None None VII.J-13 3.3.1-93 A integrit (Internal)
-Sight glass Structural Glass Treated water None None VIIJ-13 3.3.1-93 A inte.grity (Internal)
Air with-Sight glass Structural Glass borated water None None N/A N/A G integrity leakage _N/ NA_(External)
Structural Air-indoor Sight glass Glass uncontrolled None None VII.J-8 3.3.1-93 A i(External)
Enclosure A L-12-262 Page 8 of 10 Table 3.3.2-5 Aging Management Review Results -Chemical Addition System Aging Effect NUREG-Row Component Intended Material Environment Requiring Aging Management 1801, Table 1 Notes No. Type Function(s)
Management Program Volume 2 Item Item Tank -Zinc Injection Mix Structural Stainless Treated water Loss of Tank integrity Steel (Internal) material (DB- T99)Tank- Zinc Iniection Mix Structural Stainless Treated water Loss of PWR Water V11.E3-15 3.3.1-24 C Tank integrty Steel (Internal) material Chemistry (DB-T99)Tank -Zinc Air with Iniection Mix Structural Stainless borated water None None VIIJ-16 3.3.1-99 C Tank integrity Steel leakage (DB-T99) (External)
Tank -Zinc Air-indoor Iniection Structural Stainless uncontrolled None None VII. J- 15 3.3.1-94 C Tank integrity Steel (External)(DB-T99)
Enclosure A L-12-262 Page 9 of 10 Affected LRA Section LRA Page No.Affected Paragraph and Sentence A.1.10 Page A-12 2 nd Paragraph Based on the installation of the new Containment Auxiliary Crane, the 2 nd paragraph of LRA Section A.1.10, "Cranes and Hoists Inspection Program," previously revised by FENOC letter dated May 24, 2011 (ML1 1 151A090), is revised to read as follows: The Cranes and Hoists Inspection Program is based on guidance contained in ANSI B30.2 [Reference A. 1-5] for overhead and gantry cranes, ANSI B30. 11[Reference A. 1-6] for monorail systems and underhung cranes, ad-ANSI B30.16[Reference A. 1-7] for overhead hoists and ANSI B30.22 for articulating boom cranes [Reference A. 1-221. The program includes a review of the number and magnitude of lifts made by a crane, monorail or hoist.Affected LRA Section LRA Page No.Affected Paragraph and Sentence A.1.44 Page A-27 New reference listing Based on the installation of the new Containment Auxiliary Crane, a new reference listing is added to LRA Section A. 1.44, "References," previously renumbered from A.1.43 to A.1.44 by FENOC letter dated April 5, 2012 (ML12097A520), and the section is revised to read as follows: A.1.44 REFERENCES A. 1-22 ANSI B30.22, "Articulatinq Boom Cranes," 2010 Enclosure A L- 12-262 Page 10 of 10 Affected LRA Section LRA Page No. Affected Paragraph and Sentence B.2.10 Page B-52 Description, 2 nd Paragraph Based on the installation of the new Containment Auxiliary Crane, the 2 nd paragraph of LRA Section B.2.10, "Cranes and Hoists Inspection Program," previously revised by FENOC letter dated May 24, 2011 (ML1 1 151A090), is revised to read as follows: The Cranes and Hoists Inspection Program is a condition monitoring program that is based on guidance contained in American National Standards Institute (ANSI) B30.2 for overhead and gantry cranes, ANSI B30. 11 for monorail systems and underhung cranes, and-ANSI B30.16 for overhead hoists and ANSI B30.22 for articulating boom cranes. The inspections monitor structural members for signs of corrosion and wear and bolted connections for loose bolts and missing or loose nuts. The inspections are performed periodically for installed cranes and hoists. The program includes a review of the number and magnitude of lifts made by a crane, monorail or hoist.
Enclosure B Davis-Besse Nuclear Power Station, Unit No. 1 (Davis-Besse)
Letter L-12-262 New and Revised Davis-Besse License Renewal Application Boundary Drawings 5 pages follow The following License Renewal Application Boundary Drawing is new and is enclosed: LR Drawing LR-M045 Sheet I Revision 0 The following License Renewal Application Boundary Drawings are revised and are enclosed: LR Drawing LR-MOIOD Sheet I Revision 4 LR Drawing LR-M031A Revision 3 LR Drawing LR-M037D Revision 5 LR Drawing LR-M045 Revision 3 THE FOLLOWING 5 DRAWINGS SPECIFICALLY REFERENCED ENCLOSURE B DAVIS-BESSE NUCLEAR STATION, UNIT NO. 1 DOI TO D05X