Letter Sequence RAI |
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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
MONTHYEARML24303A3282024-10-29029 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-24-072, 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-24-111, 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-24-031, 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 ML24057A3362024-02-28028 February 2024 Annual Assessment Letter for Davis-Besse Nuclear Power Station (Report 05000346/2023006) IR 05000346/20230062024-02-28028 February 2024 Re-Issue 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 L-23-243, Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-0606 December 2023 Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23338A3172023-12-0606 December 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000346/2024001 IR 05000346/20234032023-11-0202 November 2023 Security Baseline Inspection Report 05000346/2023403 ML23293A0612023-11-0101 November 2023 Letter to the Honorable Marcy Kaptur, from Chair Hanson Responds to Letter Regarding Follow Up on Concerns Raised by Union Representatives During the June Visit to the Davis-Besse Nuclear Power Plant ML24045A0322023-10-26026 October 2023 L-23-221 Proposed Exam Submittal Cover Letter L-23-215, Changes to Emergency Plan2023-10-19019 October 2023 Changes to Emergency Plan ML23237B4222023-09-28028 September 2023 Energy Harbor Nuclear Corp. - Vistra Operations Company LLC - Letter Regarding Order Approving Transfer of Licenses and Draft Conforming License Amendments 2024-09-06
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24274A1482024-09-30030 September 2024 NRR E-mail Capture - Davis-Besse - RAI Re Relief Request L-23-214 ML24260A2382024-09-16016 September 2024 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information ML24249A1602024-09-0505 September 2024 Information Request to Support Upcoming Material Control and Accounting Inspection at Davis-Besse Nuclear Power Station ML24204A0012024-07-17017 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 ML24142A3532024-05-21021 May 2024 Station—Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection ML24089A2582024-04-0101 April 2024 Request for Information for the NRC Quuadrennial Comprehensive Engineering Team Inspection: Inspection Report 05000346/2024010 ML23338A3172023-12-0606 December 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000346/2024001 IR 05000346/20234022023-07-13013 July 2023 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000346/2023402 ML23131A2732023-05-15015 May 2023 Notification of NRC Supplemental Inspection 95001 and Request for Information ML23033A0322023-02-0101 February 2023 NRR E-mail Capture - Request for Additional Information for Davis-Besses 2022 Steam Generator Inspection Report (L-2022-LRO-0115) ML22357A0302022-12-23023 December 2022 Request for Information for NRC Commercial Grade Dedication Inspection: Inspection Report 05000346/2023010 ML22266A1102022-09-23023 September 2022 NRR E-mail Capture - Davis-Besse Nuclear Power Station, Unit No. 1 - Request for Additional Information Regarding July 21, 2022, Request for Withholding Information from Public Disclosure ML22214A7042022-08-0202 August 2022 Reissue - Davis-Besse Nuclear Power Station, Unit 1 Notification of Nrc Fire Protection Team Inspection Request for Information: Inspection Report 05000346/2022011 ML22187A0992022-07-0606 July 2022 Notification of NRC Supplemental Inspection (95001) and Request for Information ML22164A8572022-06-13013 June 2022 NRR E-mail Capture - Davis-Besse Nuclear Power Station, Unit No. 1 - Request for Additional Information Regarding License Amendment Request to Revise the Emergency Plan ML22118A6862022-04-28028 April 2022 NRR E-mail Capture - Davis-Besse Nuclear Power Station, Unit No. 1 - Request for Additional Information Regarding Alternative to Extend the Steam Generator Weld Inspection Interval ML22112A1092022-04-22022 April 2022 NRR E-mail Capture - Davis-Besse Nuclear Power Station, Unit No. 1 - Request for Additional Information Regarding License Amendment Request to Revise the Design Basis for the Shield Building ML22055A0872022-02-23023 February 2022 NRR E-mail Capture - Davis-Besse Nuclear Power Station, Unit No. 1 - Request for Additional Information Regarding Relief Request RP-3 IR 05000346/20210912021-12-17017 December 2021 NRC Inspection Report (05000346/2021091) Preliminary Greater than Green Finding ML21321A3792021-11-16016 November 2021 NRR E-mail Capture - Davis-Besse Nuclear Power Station, Unit No. 1 - Request for Additional Information Regarding Alternative to Extend the Steam Generator Weld Inspection Interval ML21301A0992021-10-28028 October 2021 Draft Request for Additional Information: Proposed Alternate for Examination of Steam Generator Welds - Energy Harbor Nuclear Corp., Davis-Besse Nuclear Power Station, Unit No. 1 ML21203A3252021-07-28028 July 2021 Request for Information for an NRC Triennial Baseline Design Bases Assurance Inspection (Team): Inspection Report 05000346/2021011 ML21155A1952021-06-0404 June 2021 Information Request to Support Upcoming Problem Identification and Resolution (Pi&R) Inspection at Davis Besse Nuclear Power Station ML21041A5452021-02-10010 February 2021 NRR E-mail Capture - Davis-Besse Nuclear Power Station, Unit No. 1 - Request for Additional Information Regarding Steam Generator Tube Inspection Reports 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 ML20300A5592020-10-27027 October 2020 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information ML20154K7642020-06-0202 June 2020 NRR E-mail Capture - Davis-Besse Nuclear Power Station, Unit No. 1 - Request for Additional Information Regarding License Amendment Request to Adopt TSTF-425 ML20133J9792020-05-14014 May 2020 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection 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 ML20021A3162020-01-21021 January 2020 NRR E-mail Capture - Davis-Besse Nuclear Power Station - Request for Additional Information Regarding License Amendment Request to Revise Containment Leakage Rate Testing ML19192A2222019-07-18018 July 2019 Request for Additional Information Regarding Application for Order Consenting to Transfer of Licenses and Conforming License Amendments ML19179A1382019-06-28028 June 2019 NRR E-mail Capture - Davis-Besse - Request for Additional Information Regarding the Decommissioning Quality Assurance Program ML19164A1532019-06-13013 June 2019 NRR E-mail Capture - Davis-Besse Nuclear Power Station - Request for Additional Information Regarding License Amendment Request for Post-Shutdown Emergency Plan ML19162A3922019-06-11011 June 2019 NRR E-mail Capture - Davis-Besse Nuclear Power Station - Request for Additional Information Regarding License Amendment Request for Permanently Defueled Technical Specifications 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 ML18305B0192018-11-0101 November 2018 18 Davis-Besse Nuclear Power Station - Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information(Rdb) ML18201A4122018-07-19019 July 2018 NRR E-mail Capture - Davis-Besse - Request for Additional Information Regarding License Amendment Request to Adopt NFPA 805 ML18190A4902018-07-0909 July 2018 Request for Information for an NRC Triennial Baseline Design Bases Assurance Inspection (Team), Inspection Report 05000346/2018011 (DRP-DXB) 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 ML17355A3722017-12-21021 December 2017 NRR E-mail Capture - Davis-Besse Nuclear Power Station, Unit No. 1 - Request for Additional Information Regarding License Amendment Request to Adopt NFPA 805 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 ML17257A1402017-09-14014 September 2017 NRR E-mail Capture - Davis-Besse Nuclear Power Station, Unit No. 1 - Request for Additional Information Regarding License Amendment Request to Adopt NFPA 805 ML17135A3612017-05-12012 May 2017 Information Request for NRC Triennial Evaluations of Changes, Tests, and Experiments (50.59) Baseline Inspection 05000346/2017010 (Jvb) ML17129A4112017-05-0909 May 2017 Request for Additional Information Regarding Evaluation Submitted in Response to License Renewal Commitment No. 54 ML17100A1732017-04-19019 April 2017 Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Associated Standard 805 ML16364A2792017-01-23023 January 2017 Request for Additional Information Regarding License Renewal Commitment No. 42 ML16355A0352016-12-19019 December 2016 Ltr 12/19/16 Davis-Besse Nuclear Power Station, Unit 1 - Information Request for an NRC Post-Approval Site Inspection for License Renewal 05000346/2017009 (Bxj) ML16256A0662016-10-18018 October 2016 Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Associated Standard 805 2024-09-05
[Table view] |
Text
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0 NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C, 20555*0001 I- , ;:
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Barry S. Allen, Vice President Davis-Besse Nuclear Power Station FirstEnergy Nuclear Operating Company 5501 N0I1h State Route 2 Oak Harbor, OH 43449
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE DAVIS-BESSE NUCLEAR POWER STATION (TAC NO. ME4640)
Dear Mr. Allen:
By;;atter dated August 27, 2010, FirstEnergy Nuclear Operating Company, submitted an aplplication pursuant to Title 10 of the Code of Federal Regulations (10 CFR) Part 54 for renewal of Operating License NPF-3 for the Davis-Besse Nuclear Power Station. The staff of the U.S. Nuclear Regulatory Commission (NRC or the staff) is reviewing this application in accordance with the guidance in NUREG-1800, "Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants." During its review, the staff has identified areas where additional information is needed to complete the review. The staff's requests for additional information are included in the enclosure. Further requests for additional information may be issued in the future.
Items in the enclosure were discussed with Cliff Custer, of your staff, and a mutually agreeable date for the response is within 30 days from the date of this letter. If you have any questions, please contact me by telephone at 301-415-2946 or bye-mail at SamueI.CuadradoDeJesus@nrc.gov.
Sincerely,
- J~J)/
mu~ua~rado-DZes&s, Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-346
Enclosure:
As stated cc w/encl: Listserv
DAVIS-BESSE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION REQUEST FOR ADDITIONAL INFORMATION Request for Additional Information (RAn for the Davis-Besse License Renewal Application (LRA). Sections B.2.32. "PWR Reactor Vessel Internals Program." and Section 3.1.2.
Table 3.1.2-2. "Aging Management Review Results - Reactor Vessel Internals" RAI 8.2.32-1
Background:
By letter dated December 31.2008, the Electric Power Research Institute submitted Materials Reliability Program (MRP) Report 1016596 (MRP-227), Revision (Rev.) 0, "Pressurized Water Reactor (PWR) Internals Inspection and Evaluation Guidelines," for U.S. Nuclear Regulatory Commission (NRC or the staff) review and approval.
The staff has reviewed MRP-227, Rev. 0, and determined that its guidance will provide acceptable levels of quality and safety with respect to inspection and evaluation (I&E) of reactor vessel (RV) internal components in pressurized water reactor (PWR) vessels supplied by Westinghouse, Babcock and Wilcox, and Combustion Engineering. MRP-227, Rev. provides ° I&E guidelines for implementation by license renewal applicants and licensees with renewed operating licenses in their plant-specific aging management programs (AMPs) for PWR RV internal components. However the MRP-227, Rev. 0, guidelines will be amended, as specified in the conditions and limitations identified in Section 4.1 of the staffs Safety Evaluation (SE) concerning MRP-227, Rev. 0, which is currently under development.
Section 4.2 of the SE for MRP-227, Rev. 0, identifies applicanVlicensee plant-specific action items that will need to be addressed on a plant-specific basis by license renewal applicants or licensees with renewed operating licenses. These action items address topics related to the plant-specific implementation of MRP-227, as amended by the staffs SE, that could not be effectively addressed on a generic basis in MRP-227, as amended by the staffs SE.
Applicant action item 7 from Section 4.2 of the staff's SE for MRP-227, Rev. 0, requires that license renewal applicants submit a plant-specific application to implement a new AMP for the RV internal components that is based upon the implementation of the MRP-227 guidelines, as amended by the staffs SE for MRP-227, and that applicants' AMP submittals shall include the specific information identified in items (1) through (5) in Section 3.5.1 of the SE for MRP-227, Rev. 0.
ENCLOSURE
- 2 Issue:
FirstEnergy Nuclear Operating Company (the applicant) has provided a plant-specific AMP submittal for the RV internals as part of the Davis-Besse LRA. The AMP submittal is provided in LRA Section B.2.32, "PWR Reactor Vessel Internals Program."
As stated in applicant action item 7 from Section 4.2 of the staffs SE for MRP-227, Rev. 0, the applicant's PWR RV internals AMP submittal shall include the following information identified in Section 3.5.1 of the SE for MRP-227:
° (1) An AMP for the facility shall address the 1 program elements as defined in Generic Aging Lessons Learned (GALL) Report, NUREG-1801, Rev. 2, December 2010, Chapter XI, AMP XI.M16A, "PWR Vessel Internals." The staff notes that LRA Section B.2.32 states that the Davis-Besse RV internals AMP is evaluated against the 10 elements described in Appendix A.1, Section A.1.2.3 of NUREG-1800, "Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants." LRA Section B.2.32 does not specifically address the 10 program elements defined in GALL AMP XI.M16A from Rev. 2 of the GALL.
(2) To ensure the MRP-227, Rev. 0, guidelines, as amended by the staff's SE, and the plant-specific action items identified in the staff's SE will be carried out by applicantsllicensees, applicantsllicensees are to submit an inspection plan for staff review and approval consistent with the licensing basis for the plant. The applicant has not identified any plant-specific inspection plan for ensuring the implementation of MRP-227, Rev. 0, guidelines and plant-specific action items, as identified in the staff's SE for MRP-227.
(3) Applicants for license renewal referencing MRP-227, Rev. 0, for aging management of the RV internal components shall ensure that the programs and activities specified in MRP-227, Rev. 0, as amended by the staff's SE, are summarily described in the Final Safety Analysis Report (FSAR) supplement.
(4) If the plant's current licensing basis includes specific inspection or analysis requirements for RV internal components in either the operating license for the facility or in the facility's technical speCifications (TS's), and these requirements are more comprehensive than the corresponding I&E guidelines in the MRP-227 report, as amended by the staff's SE, the requirements of the applicable license conditions or TSs take precedence over the corresponding I&E guidelines of the MRP report.
(5) Applicantsllicensees who implement MRP-227 must evaluate the current licensing basis for their facilities to determine if they have plant-specific time-limited aging analyses (TLAAs), applicable to RV internal components, which must be addressed. These
-3 TLAAs shall be submitted to the NRC for review along with the submittal for an AMP implementing MRP-227 guidelines, as modified by the staffs SE. The applicant has identified a TLAA applicable to the RV internal components. This TLAA addresses the reduction in fracture toughness for the RV internal components and is described in LRA Section 4.2.7.
The staff notes that, in order for plant-specific PWR RV internals AMPs to be consistent with GALL AMP XI.M16A from Rev. 2 of the GALL, applicants'/licensees' PWR RV internals AMP submittals must address all applicable plant-specific/vendor-specific action items established in Section 4.2 of the staff's SE for MRP-227.
Request:
The staff requests that the applicant revise the Davis-Besse PWR RV internals AMP description provided in LRA Section B.2.32 and the corresponding Updated Safety Analysis Report (USAR)
Supplement (LRA Section A.1.32) to address each of the five plant-specific AMP information requirements identified in Section 3.5.1 of the SE for MRP-227 (as required by applicant action item 7 from Section 4.2 of the staff's SE for MRP-227) as follows:
(1) LRA Section 8.2.32 should be revised to address the 10 elements of an acceptable AMP described in GALL AMP XI.M16A (GALL, Rev. 2, December 2010). Specifically, the AMP's description of the 10 elements should be revised/supplemented as follows to ensure consistency with the 10 elements in GALL AMP XI.M16A:
Element 1, Scope of Program: With respect to program scope, LRA Section B.2.32 must be supplemented to address the applicable plant-specific and vendor-specific license renewal applicant action items (LRAAls) on the MRP-227 methodology identified in Section 4.2 of the staffs SE for MRP-227, including all the programs and activities discussed in the LRAAI responses credited for aging management of reactor vessel internal (RVI) components. The staff notes that the LRAAls are identified in Section 4.2 of the staffs SE on MRP-227.
Element 2, Preventive Actions: The applicant's description of preventive actions in LRA Section B.2.32 is not consistent with Element 2 from GALL AMP XI.M16A. Please revise/supplement the description of preventive actions in LRA Section B.2.32 to ensure that it is consistent with Element 2 from GALL AMP XI.M16A.
Elements 3 through 10: Please revise/supplement the description of these program elements in LRA Section B.2.32, as necessary, to ensure that they are consistent with GALL AMP XI.M16A in Rev. 2 of NUREG-1B01.
-4 In addition to the above, please revise the subsection in LRA Section 8.2.32, titled "NUREG-1801 Consistency," to state that the corresponding AMP is described in NUREG-1801, Rev. 2, GALL Chapter XI, AMP XI.M16A and that the Davis-Besse PWR Reactor Vessel Internals Program is evaluated against the 10 elements described in GALL AMP XI,M16A.
(2) The applicant has not identified any plant-specific inspection plan in LRA Section B.2.32 for ensuring the implementation of MRP-227, Rev. 0, guidelines and plant-specific action items, as identified in the staffs SE for MRP-227. It is necessary for the applicant to either: (1) provide the plant-specific inspection plan based on the final approved version of MRP-227 and the applicant's responses to the plant-specific action items identified in the staffs SE for MRP-227; or, (2) provide a specific license renewal commitment to submit the plant-specific inspection plan to the NRC for review and approval no later than two years after issuance of the renewed operating license or two prior to the beginning of the period of extended operation, whichever is earlier.
The staff recognizes that it may not be feasible to submit an adequate inspection plan as part of this RAI response. Therefore, please supplement LRA Sections B.2.32 and A.1.32 to state that a plant-specific inspection plan for ensuring the implementation of MRP-227 program guidelines, as amended by the staffs SE for MRP-227, and Davis-Besse's responses to the plant-specific action items, as identified in the staffs SE, will be submitted for NRC staff review and approval. Also, please include a specific Davis-Besse License Renewal Commitment to submit for NRC review and approval the required plant-specific inspection plan that is based on the final approved version of MRP-227 (as modified by the staff's SE) and Davis-Besse's responses to all applicable plant-specific action items identified in the staffs SE for MRP-227. This license renewal commitment shall require the submittal of this inspection plan for NRC review and approval no later than two years after issuance of the renewed operating license or two years prior to the beginning of the period of extended operation, whichever is earlier.
(3) LRA Section A.1.32 provides the USAR supplement summary description for the Davis-Besse PWR RV Internals Program. The USAR supplement summary description for this program references the I&E guidelines of MRP-227 and states that the PWR RV Internals Program will be revised, as necessary, to incorporate the final recommendations and requirements published in the staff-approved version of MRP-227. Please include a statement in LRA Section A.1.32 indicating that the PWR RV Internals Program will address all plant-specific action items applicable to Davis-Besse that are established in Section 4.2 of the staffs SE for MRP-227.
(4) The staff found that the Davis-Besse current licensing basis TSs require that the core support shield assembly (CSS) vent valve components be inspected on a 24-month cycle. However, MRP-227, Rev. 0, Table 4-1, "B&W plants Primary components," states
- 5 that the CSS vent valve discs, top retaining ring, bottom retaining ring, disc shaft, and hinge pin will be examined using VT-3 visual methods during the next 10-year in-service inspection (lSI) interval and that subsequent VT-3 examinations will occur on the plant's 10-year ISI interval. As stated above for this item, the requirements of the applicable license conditions or TSs take precedence over the corresponding I&E guidelines of the MRP report. Therefore, based on the above discrepancy between the TS requirements and MRP guidelines for examination frequency for the CSS vent valve components, please provide the information and LRA revisions necessary for resolving this discrepancy. Specifically, either: (1) identify the applicable TS requirement as the governing inspection requirement for the CSS vent valve components, and accordingly, revise the PWR RVI AMP description in LRA Section B.2.32 to state that these TS requirements take precedence over the applicable MRP-227 I&E guidelines for the CSS vent valve components; or (2) submit the necessary TS changes, including technical justification for the proposed TS changes, to implement the less comprehensive MRP-227 I&E guidelines for the CSS vent valve components, in accordance with Title 10 of the Code of Federal Regulations (10 CFR) 54.22.
Similarly to the situation described above for the CSS vent valve components, please provide additional information concerning any other discrepancies between Davis-Besse current licensing basis requirements and the applicable MRP-227 guidelines for I&E of RVI components, and provide the information and LRA revisions necessary for resolving these discrepancies. Specifically, either; (1) identify the applicable TS requirement as the governing requirement for the component, and accordingly, revise the PWR RVI AMP description in LRA Section B.2.32 to state that the applicable TS requirements take precedence over the applicable MRP-227 I&E guidelines for the component; or, (2) submit the necessary TS changes, including technical justification for the proposed TS changes, to implement the less comprehensive MRP-227 I&E guidelines for the component, in accordance with 10 CFR 54.22.
(5) The applicant has identified one TLAA applicable to the RV internal components. This TLAA addresses the reduction in fracture toughness for the stainless steel (SS) RV internal components and is described in LRA Section 4.2.7. The description of this TLAA in LRA Section 4.2.7 is limited to the effects of neutron embrittlement on the SS RV internal components' deformation limits and the corresponding ability of the SS RV internal components to absorb local strain at the regions of maximum stress intensity.
Please supplement the PWR RV internals AMP description in LRA Section B.2.32 to state how this TLAA will be managed for the period of extended operation (i.e., that reduction in fracture toughness for RV internals will be managed in accordance with the implementation of the MRP-227 guidelines, as modified by the staff's SE, including all activities associated with Davis-Besse's responses to plant-specific action items identified in the staff's SE for MRP-227.)
- 6 RAI 8.2.32-2 According to Section A.1.4 in MRP-175, "Materials Reliability Program: PWR Internal Aging Degradation Mechanism Screening Threshold Values," susceptibility to stress corrosion cracking (SCC) in nickel-based Alloy X-7S0 PWR RV internal components depends on the type of heat treatment that is performed on the alloy. High temperature heat treatment (HTH) processes that are used on Alloy X-7S0 components offer better resistance to SCC than the other age hardened heat treatment processes. The type of heat treatment applied to Alloy X-750 PWR RV internal components is a critical parameter for ensuring that the Davis-Besse PWR RV internals AMP will adequately manage the effects of aging due to SCC for the Alloy X-750 components. Please provide information related to the type of heat treatment process that was used for the Alloy X-750 RV internal components at Davis-Besse.
Please state whether there are any RV internal components fabricated from Alloy X-750 with heat treatment other than HTH, as described above. For any such non-HTH X-7S0 RV internal components, discuss how the effects of aging due to SCC will be managed, outside the scope of the I&E guidelines described in MRP-227.
RAt 8.2.32-3 During the extended period of operation, cast austenitic stainless steel (CASS) PWR RV internal components are susceptible to a reduction in fracture toughness due to the combined effects of neutron embrittlement and thermal embrittlement, and the potential for irradiation-assisted stress corrosion cracking (IASCC). The synergistic effects of neutron embrittlement and thermal embrittlement may lead to the potential for failure of CASS RV internal components under some design basis loading conditions. Please explain how the Davis-Besse PWR RV internals AMP, as described in LRA Section B.2.32, will account for the reduction in fracture toughness due to the synergistic effects of neutron embrittlement and thermal embrittlement when evaluating CASS components to determine susceptibility to reduction in fracture toughness. The staff notes, in particular, that CASS RV internal components should be initially screened based on casting method, ferrite content, and molybdenum to determine if the components are susceptible to thermal embrittlement, and that components deemed susceptible to thermal embrittlement based on the above screening criteria should receive either supplemental examinations or a component-specific evaluation to ascertain the reduction in fracture toughness due to the synergistic effects of neutron embrittlement and thermal embrittlement.
RAI 3.1.2.2-3 LRA Table 3.1.2-2, "Aging Management Review Results - Reactor Vessel Internals," does not address certain RVI components that are listed in the Aging Management Review (AMR) line items found in Chapter IV, Section B4, "Reactor Vessel Internals (PWR) - Babcock and Wilcox,"
of the GALL Report, Rev. 2.
-7 GALL, Chapter IV, Section B4, Item No. IV.B4.RP-245 - "Core barrel assembly: (a) upper thermal shield bolts; (b) surveillance specimen holder tube bolts (Davis-Besse, only);
(c) surveillance specimen tube holder studs, and nuts (Crystal River Unit 3, only)." For this line item, the staff is only concerned with (b), "surveillance specimen holder tube bolts (Davis-Besse, only)."
GALL, Chapter IV, Section B4, Item No. 1V.B4.RP-253 - "Core support shield (CSS) assembly:
(a) CSS cast outlet nozzles (Oconee Unit 3 and Davis-Besse, only); (b) CSS vent valve discs."
For this line item, the staff is only concerned with (a), "CSS cast outlet nozzles (Oconee Unit 3 and Davis-Besse, only)."
GALL. Chapter IV, Section B4, Item Nos. IV.B4.RP-259 (lncore Monitoring Instrumentation Guide Tube Assembly), IV.B4.RP-260 (Lower Grid Assembly), IV.B4.RP-262 (Lower Grid Assembly), IV.B4.RP-261 (Lower Grid Assembly) - Each of these line items identifies specific welds in the subject assembly. These specific welds are not identified in the listing of components for the corresponding assemblies in LRA Table 3.1.2-2.
If LRA Table 3.1.2-2 addresses the subject components, as identified above, please state the Table 3.1.2-2 Row No. where these components are listed. Otherwise, please supplement LRA Table 3.1.2-2 to address these specific components (for which the staff identified a concern), as stated in the GALL. Rev. 2 AMR line items, and identify the Davis-Besse aging management programs applicable to the management of aging effects for these RV internal components.
July 11, 2011 Barry S. Allen, Vice President Davis-Besse Nuclear Power Station FirstEnergy Nuclear Operating Company 5501 North State Route 2 Oak Harbor, OH 43449
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE DAVIS-BESSE NUCLEAR POWER STATION (TAC NO. ME4640)
Dear Mr. Allen:
By letter dated August 27,2010, FirstEnergy Nuclear Operating Company, submitted an application pursuant to Title 10 of the Code of Federal Regulations (10 CFR) Part 54 for renewal of Operating License NPF-3 for the Davis-Besse Nuclear Power Station. The staff of the U.S. Nuclear Regulatory Commission (NRC or the staff) is reviewing this application in accordance with the guidance in NUREG-1800, "Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants." During its review, the staff has identified areas where additional information is needed to complete the review. The staff's requests for additional information are included in the enclosure. Further requests for additional information may be issued in the future.
Items in the enclosure were discussed with Cliff Custer, of your staff, and a mutually agreeable date for the response is within 30 days from the date of this letter. If you have any questions, please contact me by telephone at 301-415-2946 or bye-mail at Samuel. CuadradoDeJesus@nrc.gov.
Sincerely, IRA!
Samuel Cuadrado-De Jesus, Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-346
Enclosure:
As stated cc w/encl: Listserv DISTRIBUTION:
See next page ADAMS Accession No.: ML11174A191 *concurrence via e-mail OFFICE LADLR/RPB1* PM:DLR/RPB1 LA:DLR/RPB1* BC:DLR/RPB1 i NAME SFigueroa SCuadrado SFigueroa DMorey
. DATE 06/30/2011 07/01/2011 07/11/2011 07/11/2011 OFFICIAL RECORD COpy
Letter to Barry S. Allen from Samuel Cuadrado-De Jesus dated July 11, 2011
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE DAVIS-BESSE NUCLEAR POWER STATION (TAC NO. ME4640)
DISTRIBUTION:
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