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
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Category:Letter
MONTHYEARIR 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 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 ML23269A1242023-09-27027 September 2023 Request for Withholding Information from Public Disclosure IR 05000346/20234012023-09-13013 September 2023 Security Baseline Inspection Report 05000346/2023401 (Public) L-23-205, Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-09-12012 September 2023 Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments L-23-172, Quality Assurance Program Manual2023-08-31031 August 2023 Quality Assurance Program Manual IR 05000346/20230112023-08-30030 August 2023 Biennial Problem Identification and Resolution Inspection Report 05000346/2023011 ML23129A1722023-08-25025 August 2023 Request for Withholding Information from Public Disclosure for Beaver Valley Power Station, Units 1 and 2; Davis Besse Nuclear Power Station, Unit 1; and Perry Nuclear Power Plant, Unit 1 IR 05000346/20230052023-08-24024 August 2023 Updated Inspection Plan for Davis-Besse Nuclear Power Station (Report 05000346/2023005) L-23-188, Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-08-0707 August 2023 Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments IR 05000346/20230502023-08-0303 August 2023 Special Inspection Report 05000346/2023050 IR 05000346/20230902023-08-0101 August 2023 EA-23-002 Davis-Besse Nuclear Power Station - NRC Inspection Report No. 05000346/2023090 (Public) ML23178A2742023-08-0101 August 2023 Letter to the Honorable Marcy Kaptur from Chair Hanson Responds to Letter Regarding the License Transfer Application for the Davis-Besse Nuclear Power Station L-23-175, Submittal of Fifth Ten Year Inservice Testing Program2023-08-0101 August 2023 Submittal of Fifth Ten Year Inservice Testing Program IR 05000346/20230022023-07-27027 July 2023 Integrated Inspection Report 05000346/2023002 ML23193A7842023-07-13013 July 2023 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000346/2023402 ML23178A2422023-06-28028 June 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III ML23160A2342023-06-13013 June 2023 Confirmation of Initial License Examination L-23-034, 2022 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2023-06-13013 June 2023 2022 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models IR 05000346/20235012023-06-13013 June 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000346/2023501 L-23-135, Response to Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-05-31031 May 2023 Response to Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations L-23-065, Annual Financial Report2023-05-22022 May 2023 Annual Financial Report ML23124A1742023-05-17017 May 2023 Energy Harbor Fleet Vistra License Transfer - Request for Withholding Information from Public Disclosure for Commance Peak Plant, Units 1 & 2, Beaver Valley Station, Units 1 & 2, Davis Besse Station, Unit 1 and Perry Plant, Unit 1 ML23129A0112023-05-16016 May 2023 Notice of Consideration of Approval of Indirect and Direct License Transfer for Comanche Peak Plant, Units 1 & 2, Beaver Valley Station, Units 1 & 2, Davis Besse Station, Unit 1 and Perry Plant, Unit 1 (EPID L-2023-LLM-0000) (Letter) ML23131A2732023-05-15015 May 2023 Notification of NRC Supplemental Inspection 95001 and Request for Information L-23-101, Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report for the Davis-Besse Nuclear Power Station - 20222023-05-12012 May 2023 Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report for the Davis-Besse Nuclear Power Station - 2022 L-23-131, Readiness for Resumption of NRC Supplemental Inspection2023-05-12012 May 2023 Readiness for Resumption of NRC Supplemental Inspection IR 05000346/20230102023-05-0909 May 2023 Commercial Grade Dedication Inspection Report 05000346/2023010 ML23123A1272023-05-0303 May 2023 Information Request to Support Upcoming Problem Identification and Resolution Inspection at Davis-Besse Nuclear Power Station IR 05000346/20230012023-05-0101 May 2023 Integrated Inspection Report 05000346/2023001 and 07200014/2022001 L-23-092, Occupational Radiation Exposure Report for Year 20222023-04-27027 April 2023 Occupational Radiation Exposure Report for Year 2022 ML23111A1972023-04-26026 April 2023 Information Meeting with Question and Answer Session to Discuss NRC 2022 End-of-Cycle Plant Performance Assessment of Davis-Besse Nuclear Power Plant Station ML23114A1062023-04-25025 April 2023 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection CP-202300181, ISFSI, Beaver Valley, Units 1 and 2, ISFSI, Davis-Besse, Unit 1, ISFSI, Perry, Unit 1, ISFSI, Corrected Affidavit for Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-04-20020 April 2023 ISFSI, Beaver Valley, Units 1 and 2, ISFSI, Davis-Besse, Unit 1, ISFSI, Perry, Unit 1, ISFSI, Corrected Affidavit for 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 ML23096A1382023-04-11011 April 2023 Review of the Spring 2022 Steam Generator Tube Inspection Report L-23-061, Submittal of the Decommissioning Funding Status Reports2023-03-31031 March 2023 Submittal of the Decommissioning Funding Status Reports L-23-037, and Perry Nuclear Power Plant - Independent Spent Fuel Storage Installation Changes, Tests, and Experiments2023-03-29029 March 2023 and Perry Nuclear Power Plant - Independent Spent Fuel Storage Installation Changes, Tests, and Experiments L-23-066, Annual Notification of Property Insurance Coverage2023-03-21021 March 2023 Annual Notification of Property Insurance Coverage ML23066A2892023-03-14014 March 2023 Request for Threshold Determination Under 10 CFR 50.80 and 10 CFR 72.50 for an Amendment to the Voting Agreement ML23066A2592023-03-14014 March 2023 Request for Withholding Information from Public Disclosure for Beaver Valley Power Station, Units 1 and 2, Davis Besse Nuclear Power Station, Unit 1, and Perry Nuclear Power Plant, Unit 1 2024-02-02
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML23338A3172023-12-0606 December 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000346/2024001 ML23193A7842023-07-13013 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-Besse's 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 ML16196A0152016-07-22022 July 2016 Request for Additional Information Regarding Amendment Request to Revise Emergency Action Level Scheme L-16-122, Completion of Required Action by NRC Order EA-12-051, Reliable Spent Fuel Pool Instrumentation2016-06-24024 June 2016 Completion of Required Action by NRC Order EA-12-051, Reliable Spent Fuel Pool Instrumentation ML16060A0122016-02-29029 February 2016 FENOC - Email RAI to Licensee Regarding LAR for Changes to TS 5.3.1 CAC Nos. MF7118, MF7119, and MF7120 ML16047A1452016-02-22022 February 2016 Supplemental Information Needed for Acceptance of License Amendment Request to Adopt National Fire Protection Associated Standard 805 ML16019A3972016-01-20020 January 2016 Request for Additional Information Related to Amendment Request for Emergency Diesel Generator Minimum Voltage Surveillance Requirements ML15222A1792015-09-21021 September 2015 Request for Additional Information Related to Amendment Request for Emergency Diesel Generator Minimum Voltage Surveillance Requirements (TAC No. MF6060)(L-15-117) 2023-07-13
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Text
UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 October 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 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 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, Iicu(1.d!lls, Project Manager 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 LICENSE RENEWAL REQUEST FOR ADDITIONAL RAI 8.2.40-3 Follow-Up to RAI By letter dated August 17, 2011, the applicant responded to a staff RAI regarding experience with degradation of the north embankment of the safety-related portion of the canal. In the response the applicant committed to ensure that an investigation of embankment degradation would be completed prior to the period of extended operation. applicant further committed to evaluate the results and complete needed repairs modifications of the embankment prior to the period of extended Although the applicant committed to completing long-term evaluation plans, no information provided about the plan, such as schedule, scope, or acceptance Provide details about the embankment investigation.
The response should include information, activities planned and completed to date, and probable corrective actions. response should provide technical justification for the timeliness of the repairs, including explanation why prior to the period of extended operation is an acceptable deadline completing the License renewal application (LRA) Section 4.7.3 discusses a fracture mechanics analysis evaluating the integrity of the reactor vessel (RV) during the pressurized thermal shock event associated with low-temperature (35 OF) water injection from the borated water tank (BWST) following a small steam line break. LRA Section 4.7.3 states that the licensing basis (CLB) analysis for this event is addressed in the Davis-Besse Updated Analysis Report (USAR), Section 5.2 and that the subject analysis was revised to consider period of extended operation (52 The staff reviewed USAR Section 5.2 and could not locate the CLB analysis for evaluating integrity under the subject PTS conditions.
Furthermore, the staff found no references in Section 4.8 for reports documenting the analysis of RV integrity under these PTS conditions the period of extended operation, based on the 52 EFPY reference temperature for PTS (RT State the USAR section and page number where the summary of the CLB analysis of the subject PTS event is located. If a summary of the CLB analysis is not located in the USAR, please state where it can be found. ENCLOSURE Provide the reports documenting the projected 52 EFPY analysis of RV integrity under the subject PTS conditions.
RAI4.7.4-1
Background:
By letter dated June 3, 2011, the applicant provided Amendment 8 to Davis-Besse LRA. LRA Amendment 8 revised the disposition for the analysis of the HPI/Makeup Nozzle Thermal Sleeves in LRA Section 4.7.4 from "10 CFR 54.21 (c)(1)(iii)" to "Not a TLAA." As an explanation for the revised disposition, LRA Section 4.7.4, as amended, now states that U[b]ased on the [USAR Supplement]
commitment
[to replace the subject thermals sleeves], the HPI/Makeup nozzle thermal sleeves are short-lived (not 40-year) parts and therefore this analysis is not a TLAA." Similarly, LRA Amendment 8 revised the corresponding USAR Supplement section in LRA Section A.2.7.4 to reflect the changed disposition.
LRA Section A.2.7.4, as revised by LRA Amendment 8, now states that, U[b]ased on the commitment
[to replace the subject thermal sleeves], the HPI/makeup nozzle thermal sleeves are short lived (not 40-year) parts and therefore this analysis is not a TLAA." Finally, LRA Section 4.1, Table 4.1-1, was amended per LRA Amendment 8 to state that the evaluation of the subject thermal sleeves is "Not a TLAA." Issue: The staff determined that aging of the subject thermal sleeves, as discussed in LRA Section 4.7.4. should be identified as a time-limited aging analysis (TLAA) in LRA Sections 4.1, 4.7.4, and the USAR Supplement, because the aging mechanism is time dependent (Le., it is dependent on the number of transient cycles incurred), and the staff cannot accept future commitments to replace components as a means for disposition of the currently-installed components undergoing time-dependent aging processes, without a TLAA of the currently installed components.
Reguest: Based on the above, the staff requests that the applicant amend LRA Sections 4.1,4.7.4, and A.2.7.4 to identify HPI/makeup thermal sleeve aging as a TLAA. The staff also requests that the applicant select an appropriate disposition under Title 10 of the Code of Federal Regulations (10 CFR 54.21(c)(1>>.
If the applicant proposes a 10 CFR 54.21 (c)(1)(iii) disposition for this analysis, then the staff requests that the applicant amend LRA Sections 4.7.4 and A.2.7.4 to propose an appropriate aging management program (AMP) for managing the effects of aging on the intended function of the thermal sleeves. Any AMP identified in LRA Sections 4.7.4 and A.2.7.4 for a 10 CFR 54.21 (c)(1)(iii) disposition of this analysis should ensure that the effects of aging on the subject thermal sleeves are appropriately managed for the period of extended operation.
RAI 4.7.5.2-2
Background:
LRA Section 4.7.5.2 addresses the TLAA related to the steam generator 1-2 flaw evaluations.
LRA Section 4.7.5.2 states that the subject flaws were analytically evaluated using the ASME Code,Section XI, IWB-3612 acceptance criteria.
LRA Section 4.7.5.2 further states that the IW8-3612 analysis of the subject flaws determined that the steam generator shell components containing the flaws would remain acceptable for continued service during the period of extended operation, accounting for flaw growth due to fatigue based on 240 heat-up and cool-down cycles. By letter dated March 17, 2011 (ADAMS Accession No. ML110680172) the NRC staff submitted a request for additional information (RAI) concerning the plant-specific TLAAs in the Davis-Besse LRA, Sections 4.7.4,4.7.5.1, and 4.7.5.2. The staff issued RAI 4.7.5.2-1 to request clarification on a number of issues concerning the subject steam generator shell flaws and the ASME Code,Section XI, IWB-3612 analytical evaluations of these flaws. In RAI4.7.5.2-1, part (b), the staff requested that the applicant state whether the subject flaws were found to be the result of service-induced degradation or fabrication defects. In RAI 4.7.5.2-1, part (e) the staff requested that the applicant state whether the flaw dimensions have increased since discovery in 1988. The staff also requested that, if the flaw dimensions have increased, the applicant state whether the subject flaws were re-analyzed in accordance*
with ASME Code,Section XI, IWB-3612 requirements based on the new flaw dimensions.
In RAI4.7.5.2-1, part (g), the staff requested that the applicant provide references for all reports documenting IWB-3612 analytical evaluations of the subject flaws. Issue: By letter dated April 15, 2011, the applicant submitted its responses to the staffs RAls. In its response to RAI 4.5.2.1, part (b), the applicant stated that the subject flaws "were analyzed in accordance with IWB-3612, as required by the ASME [Code],Section XI acceptance standards, and found to be acceptable for continued operation." The staff reviewed the applicant's response to RAI4.7.5.2-1, part (b) and noted that the applicant did not state whether the subject flaws were determined to be service-induced or caused by fabrication.
In its response to RAI 4.7.5.2-1, part (e), the applicant stated that "[t]he subject components were reexamined during Cycle 6 (year 1990) and no flaw growth was noted. The subject components, with the exception of the W axis longitudinal seam weld intersection with the shell to lower tubesheet weld, were also reexamined during Cycle 7 (year 1991) and no flaw growth was noted." The staff reviewed the applicant's response to RAI 4.7.5.2-1, part (e), and noted that the RAI response only stated that no Haw growth was noted during the ASME Code, Section IWC-2420(b)-required successive inspections performed in 1990 and the subsequent inspections performed in 1991. The staff noted that the applicant did not state whether any flaw growth was noted for the subject components as a result of any examinations performed on the flawed regions after 1991. In its response to RAI 4.7.5.2-1, part (g), the applicant stated that the subject flaw evaluations are documented in the following Babcock & Wilcox (B&W) Reports from 1988: 1. Report No. 32-1172294-00, "Davis-Besse 1 SG Flaw Evaluation," dated June 9,1988 2. Report No. 32-1172294-01, "Davis-Besse 1 SG Flaw Evaluation," dated July 18, 1988 3. Report No. 32-1172523-00, "DB-1 SG Flaw Evaluation," dated July 18,1988 The above flaw evaluation reports were provided in an enclosure to the April 15, 2011 RAI response.
These flaw evaluation reports reference the 1977 Edition of the ASME Code,Section XI, IWB-3612 analytical acceptance standard.
The flaw evaluation report summaries state that the subject flaws were found to be acceptable, in accordance with the ASME Code,Section XI, IWB-3612 analytical acceptance standard.
In reviewing the above flaw evaluation reports, the staff determined that the subject evaluations were only performed for normal conditions, and only demonstrated based on the analytical acceptance criterion for normal (including upset and test) conditions, as specified in the ASME Code,Section XI, IWB-3612, paragraph (a). The determined that the applicant had not specifically evaluated the subject flaws for emergency faulted conditions, as required by the 1977 Edition of the ASME Code,Section XI, paragraph Based on the above, the staff requests that the applicant provide the following concerning the subject steam generator flaws and the analytical evaluations performed for (1) Taking into consideration the steam generator shell materials containing the flaws, the secondary side water and steam environment, and the secondary side thermal and pressure stresses to which these shell components are subjected, please state whether any of the surface-breaking indications were believed to have been caused by stress corrosion cracking, or any other service-induced aging effect. (2) For any in service examinations performed on the flawed regions of the steam generator shell after 1991, in particular the examinations performed for the steam generator XIY axis outlet nozzle to shell weld and the lower tubesheet to shell weld during the first and second periods of the third 10-year lSI interval, please state whether these examinations detected any increase in the flaw dimensions, relative to the 1988 flaw dimensions. (The staff notes that any measured increase in flaw dimensions would likely invalidate the analyses performed in the 1988 flaw evaluation reports.)
(3) Please state whether the subject flaws were analyzed for emergency and faulted conditions, as required by the ASME Code,Section XI, IWB-3612, paragraph (b). If the subject flaws were analyzed for emergency and faulted conditions, as required by IWB-3612, paragraph (b), please provide the flaw analyses for these conditions, or explain how the IWB-3612, paragraph (a) analyses, as documented in the 1988 flaw evaluation reports, for normal, upset, and test conditions, would bound the flaw analyses for emergency and faulted conditions.
If the subject flaws were not analyzed for emergency and faulted conditions, please provide these analyses, as required by IWB-3612, paragraph (b).
October 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 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 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'.. "concurrence via e-mail OFFICE LA:DLR* PM:RPB1 :DLR BC:RPB1 :DLR PM:RPB1 :DLR NAME SFigueroa SCuadrado DMorey SCuadrado DATE 10/5/2011 1017/2011 10110/2011 10111/2011 OFFICIAL RECORD COpy Letter to Barry S. Allen from Samuel Cuadrado-De Jesus dated October 11, 2011 REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE DAVIS-BESSE NUCLEAR POWER STATION (TAC NO. ME4640) DISTRIBUTION:
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