Letter Sequence Other |
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TAC:ME4640, Steam Generator Tube Integrity (Approved, Closed) |
Results
- Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval
Other: L-11-114, Drawing No. M-042B, Rev. 35, Sampling System Sh. 2 Local Grab Samples, L-11-131, Drawing No. LR-OS041A2, Revision 1, Operational Schematic Emergency Diesel Generator Systems., L-11-334, Reply to Request Additional Information for the Review of the License Renewal Application Amendment No. 21, L-12-337, Review of the Safety Evaluation Report with Open Items Related to the License Renewal, L-12-444, Submittal of Contractor Equivalent Margins Assessments for Reactor Vessel Welds (Nonproprietary Versions), L-12-456, Notification of Closure of Commitments Related to the Review of the License Renewal Application, L-13-257, Notification of Completion of a License Renewal Commitment Related to the Review of License Renewal Application TAC No. ME4640) and License Renewal Application Amendment No. 45), L-13-330, License Renewal Application Amendment No. 46 - Annual Update, L-13-341, Review of the Safety Evaluation Report Related to the License Renewal of Davis-Besse Nuclear Power Station, L-14-085, License Renewal Application (TAC No. ME4640) Amendment No. 48, L-14-206, License Renewal Application Amendment No. 50 - Annual Update, L-15-120, Notification of Completion of License Renewal Commitments Related to the Review of the Davis-Besse Nuclear Power Station, Unit No. 1, License Renewal Application and License Renewal Application Amendment No. 55, L-15-139, License Renewal Reactor Vessel Internals Inspection Plan, L-15-214, License Renewal Application Amendment No. 59 - Annual Update, L-15-309, License Renewal Application Amendment No. 60, L-15-310, C-CSS-099.20-069, Rev 0, Shield Building Laminar Cracking Limits., ML102450565, ML111050091, ML11110A089, ML11110A091, ML11110A092, ML11110A093, ML11110A094, ML11110A095, ML11110A105, ML11110A106, ML11110A107, ML11122A014, ML11126A017, ML11126A018, ML11126A019, ML11126A020, ML11126A021, ML11126A022, ML11126A023, ML11126A024, ML11126A025, ML11126A026, ML11126A032, ML11126A033, ML11126A034, ML11126A035, ML11126A036, ML11126A037, ML11126A038, ML11126A039, ML11126A040, ML11126A041, ML11126A042, ML11126A043... further results
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MONTHYEARML11126A0882008-01-12012 January 2008 Drawing No. LR-M041B, Revision 1, Piping & Instrument Diagram Primary Service Water System. Job Code 12501 Project stage: Other ML11126A0902008-01-15015 January 2008 Drawing No. LR-OS41A1, Revision 1, Operational Schematic Emergency Diesel Generator Systems. Project stage: Other L-11-131, Drawing No. LR-OS041A2, Revision 1, Operational Schematic Emergency Diesel Generator Systems.2008-01-15015 January 2008 Drawing No. LR-OS041A2, Revision 1, Operational Schematic Emergency Diesel Generator Systems. Project stage: Other ML11126A0682008-05-0505 May 2008 Drawing No. LR-M-037E, Revision 28, Piping & Instrument Diagram Clean Liquid Radioactive Waste System. Project stage: Other ML11126A0652008-08-0606 August 2008 Drawing No. LR-M036B, Revision 1, Piping & Instrument Diagram Component Cooling Water System. Project stage: Other ML11126A0592008-10-0909 October 2008 Drawing No. LR-M033A, Revision 1, Piping & Instrument Diagram High Pressure Injection. Project stage: Other ML11126A0632008-10-10010 October 2008 Drawing No. LR-M033B, Revision 1, Piping & Instrument Diagram Decay Heat Train 1. Project stage: Other ML11126A0702008-10-10010 October 2008 Drawing No. LR-M033C, Revision 1, Piping & Instrument Diagram Decay Heat Train 2. Project stage: Other ML11126A0742008-11-0606 November 2008 Drawing No. LR-M043, Revision 1, Piping & Instrument Diagram Auxiliary Building Chilled Water System. Project stage: Other ML11126A0832008-12-18018 December 2008 Drawing No. LR-M038C, Revision 2, Piping & Instrument Diagram Gaseous Radioactive Waste System. Job Code 12501 Project stage: Other ML11126A0712009-04-0707 April 2009 Drawing No. LR-M034, Revision 1, Piping & Instrument Diagram Emerg. Core Cooling System Ctmt. Spray & Core Flooding Systems. Project stage: Other ML11126A0892009-04-0707 April 2009 Drawing No. LR-OS002, Revision 1, Operational Schematic Makeup and Purification System. Project stage: Other ML1024505652010-08-27027 August 2010 License Renewal Application and Ohio Coastal Management Program Consistency Certification Project stage: Other ML1104500462011-02-17017 February 2011 Request for Additional Information for the Review of the Davis-Besse Nuclear Power Station - Fire Protection Project stage: RAI ML11126A0792011-02-25025 February 2011 Drawing No. LR-M900A, Revision 0, Instrument Air System Piping Schematic. Project stage: Other ML1104205972011-02-28028 February 2011 Request for Additional Information for the Review of the Davis-Besse Nuclear Power Station - Section 2.4 Project stage: RAI ML1106801722011-03-17017 March 2011 Request for Additional Information on the Reactor Vessel Surveillance Aging Management Program, Time-Limited Aging Analyses for Neutron Embrittlement of the Rv and Internals, and Other TLAAs for the Review of the Davis-Besse Nuclear Power S Project stage: RAI ML1107007322011-03-18018 March 2011 Request for Additional Information for the Review of the Davis-Besse Nuclear Power Station-Section 2.2 & 2.3 Project stage: RAI L-11-078, Reply to Request for Additional Information for the Review of License Renewal Application (TAC ME4640) Amendment No. 12011-03-18018 March 2011 Reply to Request for Additional Information for the Review of License Renewal Application (TAC ME4640) Amendment No. 1 Project stage: Response to RAI ML11068A0002011-03-21021 March 2011 Request for Additional Information for the Review of the Davis-Besse Nuclear Power Station - Section 4.7 (TAC Number ME4640) Project stage: RAI L-11-079, Reply to Request for Additional Information for the Review of the License Renewal Application2011-03-23023 March 2011 Reply to Request for Additional Information for the Review of the License Renewal Application Project stage: Response to RAI L-11-089, Reply to Request for Additional Information for the Review License Renewal Application2011-03-23023 March 2011 Reply to Request for Additional Information for the Review License Renewal Application Project stage: Response to RAI ML1108206242011-03-30030 March 2011 Request for Additional Information for the Review of the Davis-Besse Nuclear Power Station-Section 2.1 (Tac No. ME4640) Project stage: RAI ML1109002952011-03-31031 March 2011 Safety Evaluation Report Related to the License Renewal of Salem Nuclear Generating Station Project stage: Approval ML1108204902011-04-0505 April 2011 Request for Additional Information for the Review of the Davis-Besse Nuclear Power Station - Batch 1 Project stage: RAI ML11110A0932011-04-15015 April 2011 Drawing No. M-037D, Rev. 21, Clean Liquid Radioactive Waste System Project stage: Other ML11110A1072011-04-15015 April 2011 Drawing No. M-045, Rev. 56, Chemical Addition Systems Project stage: Other ML11110A1062011-04-15015 April 2011 Drawing No. M-042C, Rev. 33, Sampling System Sh. 3 Project stage: Other ML11110A1052011-04-15015 April 2011 Drawing No. M-040A, Rev. 76, Reactor Coolant System Details Project stage: Other ML11110A0952011-04-15015 April 2011 Drawing No. M-039B, Rev. 18, Miscellaneous Liquid Radioactive Waste Project stage: Other ML11110A0942011-04-15015 April 2011 Drawing No. M-039A, Rev. 33, Miscellaneous Liquid Radioactive Waste Project stage: Other ML11110A0922011-04-15015 April 2011 Drawing No. M-037C, Rev. 30, Clean Liquid Radioactive Waste System Project stage: Other L-11-114, Drawing No. M-042B, Rev. 35, Sampling System Sh. 2 Local Grab Samples2011-04-15015 April 2011 Drawing No. M-042B, Rev. 35, Sampling System Sh. 2 Local Grab Samples Project stage: Other L-11-107, Reply to Request for Additional Information on Reactor Vessel Surveillance Aging Management Program & Time-Limited Aging Analyses for Neutron Embrittlement for Review of License Renewal Application & License Renewal Application...2011-04-15015 April 2011 Reply to Request for Additional Information on Reactor Vessel Surveillance Aging Management Program & Time-Limited Aging Analyses for Neutron Embrittlement for Review of License Renewal Application & License Renewal Application... Project stage: Response to RAI ML11110A0882011-04-15015 April 2011 Reply to Request for Additional Information for the Review of the License Renewal Application, Sections 2.2 & 2.3, License Renewal Application Amendment No. 3, and Revised License Renewal Project stage: Response to RAI ML11110A0912011-04-15015 April 2011 Drawing No. M-011, Rev. 61, Domestic Water System Project stage: Other ML11110A0892011-04-15015 April 2011 Drawing No. M-0060, Rev. 52, Auxiliary Feedwater System Project stage: Other ML1110500912011-04-19019 April 2011 Scoping and Screening Audit Report Regarding the Davis-Besse Nuclear Power Station License Renewal Application Project stage: Other L-11-115, Reply to Request for Additional Information for the Review of the License Renewal Application and License Renewal Application Amendment No. 42011-04-20020 April 2011 Reply to Request for Additional Information for the Review of the License Renewal Application and License Renewal Application Amendment No. 4 Project stage: Response to RAI ML1109807182011-04-20020 April 2011 Request for Additional Information for the Review of the Davis-Bessie Nuclear Power Station - Batch 2 Project stage: RAI ML11126A0362011-04-29029 April 2011 Drawing No. LR-M017D, Revision 1 Piping & Instrument Diagram, Steam Blackout Diesel Generator. Project stage: Other ML11126A0352011-04-29029 April 2011 Drawing No. LR-M017C, Revision 2, Piping & Instrument Diagram, Fuel Oil. Project stage: Other ML11126A0342011-04-29029 April 2011 Drawing No. LR-M017B, Revision 1, Piping & Instrument Diagram, Diesel Generators Air Start. Project stage: Other ML11126A0332011-04-29029 April 2011 Drawing No. LR-M016B, Revision 1, Piping & Instrument Diagram Station Fire Protection System Project stage: Other ML11126A0322011-04-29029 April 2011 Drawing No. LR-M016A, Revision 1, Piping & Instrument Diagram Station Fire Protection System Project stage: Other ML11126A0262011-04-29029 April 2011 Drawing No. LR-M010C, Revision 1, Piping & Instrument Diagram Make-up Water Treatment System Project stage: Other ML11126A0252011-04-29029 April 2011 Drawing No. LR-M010A, Revision 1, Piping & Instrument Diagram Make-Up Water Treatment System Project stage: Other ML11126A0242011-04-29029 April 2011 Drawing No. LR-M009B, Revision 1, Piping & Instrument Diagram Cooling Water System Project stage: Other ML11126A0192011-04-29029 April 2011 Drawing No. LR-M003A, Revision 1, Piping & Instrument Diagram Main Steam and Reheat System. Sheet 1 Project stage: Other ML11126A0452011-04-29029 April 2011 Drawing No. LR-M024H, Revision 1, Piping & Instrument Diagram, No. 2 Main and Auxiliary Turbine Driven Feed Pumps. Project stage: Other 2011-02-25
[Table View] |
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Category:Legal-Affidavit
MONTHYEARL-23-065, Annual Financial Report2023-05-22022 May 2023 Annual Financial Report 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 L-22-229, Response to Request for Additional Information Regarding Request to Withhold Information in Framatome Inc. Document ANP-2718P-007 from Public Disclosure & Affidavit2022-10-13013 October 2022 Response to Request for Additional Information Regarding Request to Withhold Information in Framatome Inc. Document ANP-2718P-007 from Public Disclosure & Affidavit L-22-057, Annual Financial Report - Affidavit2022-05-25025 May 2022 Annual Financial Report - Affidavit L-22-141, Enclosure D: Affidavit of Elliott Gayle2022-04-0808 April 2022 Enclosure D: Affidavit of Elliott Gayle L-21-041, Annual Financial Report - Affidavit2021-12-14014 December 2021 Annual Financial Report - Affidavit L-21-093, Enclosure B - Affidavit of Philip A. Opsal and Enclosure C: Rev. 1 to ANP-3438NP, MRP-227-A - Applicant/Licensee Action Item 7 Analysis for Davis-Besse Nuclear Power Station Unit 1 (Non-Proprietary)2021-02-0404 February 2021 Enclosure B - Affidavit of Philip A. Opsal and Enclosure C: Rev. 1 to ANP-3438NP, MRP-227-A - Applicant/Licensee Action Item 7 Analysis for Davis-Besse Nuclear Power Station Unit 1 (Non-Proprietary) L-20-126, Request for Threshold Determination - Corporate Organization and Ownership2020-05-0404 May 2020 Request for Threshold Determination - Corporate Organization and Ownership L-20-067, Retrospective Premium Guarantee - 2020 Internal Cash Flow Projection2020-03-0404 March 2020 Retrospective Premium Guarantee - 2020 Internal Cash Flow Projection L-19-200, ISFSI, Davis-Besse, Unit 1, ISFSI, Perry, Unit 1, ISFSI - Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2019-08-29029 August 2019 ISFSI, Davis-Besse, Unit 1, ISFSI, Perry, Unit 1, ISFSI - Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments ML22202A4312019-04-25025 April 2019 Enclosure a: Affidavit L-17-190, Response to Request for Information Regarding License Renewal Commitment No. 542017-06-0808 June 2017 Response to Request for Information Regarding License Renewal Commitment No. 54 L-16-028, Retrospective Premium Guarantee2016-03-0202 March 2016 Retrospective Premium Guarantee ML15299A1432015-10-19019 October 2015 Additional Information for the Advisory Committee on Reactor Safeaquards Review of the License Renewal Application, Including Enclosure a, Bechtel Affidavit ML15113B1342015-04-21021 April 2015 to ANP-3285, Confirmation of Stress Relief for the DB-1 Core Support Shield Upper Flange Weld and Revision 0 to ANP-3359NP, Davis-Besse Reactor Vessel Internals License Renewal Scope and MRP-189, Revision 1 Comparison. (Non-Proprietary) ML0615704702006-06-0505 June 2006 David Geisen - Affidavit of Robert D. Starkey ML0611401302006-03-16016 March 2006 Ltr Fm J. Gutierrez, Morgan Lewis to S. Brock Requesting to Withhold Materials from Public Disclosure Which Was Submitted by FENOC - Affidavits of Terry Young and Warren Bilanin ML0413104202004-05-0303 May 2004 LB Order (Granting Motion to Extend Time for Filing Reply) ML0415501942004-04-29029 April 2004 Notice of Filing of Declarations in Support of Petitioners' Standing to Sue ML0213305262002-05-0101 May 2002 Cycle 14 Fuel & Core Description. Without Enclosures 2023-05-22
[Table view] Category:Letter
MONTHYEARML24281A0662024-10-0404 October 2024 EN 57363 - MPR Associates, Inc. Report in Accordance with 10 CFR Part 21 on Incomplete Dedication of Contactors Supplied as Basic Components IR 05000346/20244032024-09-27027 September 2024 Security Baseline Inspection Report 05000346/2024403 ML24269A0552024-09-25025 September 2024 Submittal of the Updated Final Safety Analysis Report, Revision 35 05000346/LER-2021-001-01, Emergency Diesel Generator Speed Switch Failure Due to Direct Current System Ground2024-09-19019 September 2024 Emergency Diesel Generator Speed Switch Failure Due to Direct Current System Ground ML24134A1522024-09-17017 September 2024 Exemption from the Requirements of 10 CFR 50.71(e)(4) Final Safety Analysis Report Update Schedule (EPID L-2024-LLE-0005) - Letter ML24260A2382024-09-16016 September 2024 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information ML24255A8032024-09-11011 September 2024 Technical Specification 5.6.6 Steam Generator Tube Inspection 180-Day Report ML24255A8642024-09-0606 September 2024 Rscc Wire & Cable LLC Dba Marmon Industrial Energy & Infrastructure - Part 21 Retraction of Final Notification ML24249A1602024-09-0505 September 2024 Information Request to Support Upcoming Material Control and Accounting Inspection at Davis-Besse Nuclear Power Station L-24-188, Submittal of Quality Assurance Program Manual, Revision 302024-08-27027 August 2024 Submittal of Quality Assurance Program Manual, Revision 30 ML24239A3972024-08-23023 August 2024 Rssc Wire & Cable LLC Dba Marmon - Part 21 Final Notification - 57243-EN 57243 IR 05000346/20240052024-08-22022 August 2024 Updated Inspection Plan for Davis-Besse Nuclear Power Station (Report 05000346/2024005) L-24-186, Response to RAI for Exemption Request from 10 CFR 50.71(e)(4) Final Safety Analysis Update Schedule2024-08-15015 August 2024 Response to RAI for Exemption Request from 10 CFR 50.71(e)(4) Final Safety Analysis Update Schedule IR 05000346/20240022024-08-0101 August 2024 Integrated Inspection Report 05000346/2024002 IR 05000346/20244012024-07-30030 July 2024 Security Baseline Inspection Report 05000346/2024401 ML24208A0962024-07-25025 July 2024 57243-EN 57243 - Rssc Wire & Cable LLC, Dba Marmon - Part 21 Notification L-24-032, Cycle 23 and Refueling Outage 23 Inservice Inspection Summary Report2024-07-15015 July 2024 Cycle 23 and Refueling Outage 23 Inservice Inspection Summary Report L-24-063, License Amendment Request to Remove the Table of Contents from the Technical Specifications2024-07-0808 July 2024 License Amendment Request to Remove the Table of Contents from the Technical Specifications L-24-024, Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2024-06-19019 June 2024 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models L-23-214, Submittal of Relief Request for Impractical American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI Examination Requirements2024-06-0505 June 2024 Submittal of Relief Request for Impractical American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI Examination Requirements L-24-019, Unit No.1 - Report of Facility Changes, Tests, and Experiments2024-05-22022 May 2024 Unit No.1 - Report of Facility Changes, Tests, and Experiments ML24142A3532024-05-21021 May 2024 Station—Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection L-24-111, Response to Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-05-15015 May 2024 Response to Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations L-24-072, Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report - 20232024-05-15015 May 2024 Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report - 2023 L-24-031, Unit No.1 - Steam Generator Tube Circumferential Crack Report - Spring 2024 Refueling Outage2024-05-14014 May 2024 Unit No.1 - Steam Generator Tube Circumferential Crack Report - Spring 2024 Refueling Outage IR 05000346/20240012024-05-0303 May 2024 Integrated Inspection Report 05000346/2024001 L-24-069, Occupational Radiation Exposure Report for Year 20232024-04-30030 April 2024 Occupational Radiation Exposure Report for Year 2023 L-24-018, Submittal of Core Operating Limits Report, Cycle 24, Revision 02024-04-16016 April 2024 Submittal of Core Operating Limits Report, Cycle 24, Revision 0 ML24089A2582024-04-0101 April 2024 Request for Information for the NRC Quuadrennial Comprehensive Engineering Team Inspection: Inspection Report 05000346/2024010 L-24-013, Annual Notification of Property Insurance Coverage2024-03-26026 March 2024 Annual Notification of Property Insurance Coverage ML24036A3472024-03-0707 March 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0076 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML24057A0752024-03-0101 March 2024 the Associated Independent Spent Fuel Storage Installations IR 05000346/20230062024-02-28028 February 2024 Re-Issue Annual Assessment Letter for Davis-Besse Nuclear Power Station (Report 05000346/2023006) ML24057A3362024-02-28028 February 2024 Annual Assessment Letter for Davis-Besse Nuclear Power Station (Report 05000346/2023006) L-23-264, Request for Exemption from 10 CFR 50.71(e)(4) Final Safety Analysis Report Update Schedule2024-02-23023 February 2024 Request for Exemption from 10 CFR 50.71(e)(4) Final Safety Analysis Report Update Schedule CP-202300502, Notice of Planned Closing of Transaction and Provision of Documents to Satisfy Order Conditions2024-02-23023 February 2024 Notice of Planned Closing of Transaction and Provision of Documents to Satisfy Order Conditions L-24-050, Retrospective Premium Guarantee2024-02-22022 February 2024 Retrospective Premium Guarantee IR 05000346/20243012024-02-0202 February 2024 NRC Initial License Examination Report 05000346/2024301 IR 05000346/20230042024-01-31031 January 2024 Integrated Inspection Report 05000346/2023004 ML23313A1352024-01-17017 January 2024 Authorization and Safety Evaluation for Alternative Request RP 5 for the Fifth 10 Year Interval Inservice Testing Program ML23353A1192023-12-19019 December 2023 Operator Licensing Examination Approval Davis Besse Nuclear Power Station, January 2024 L-23-260, Corrections to the 2022 Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report for the Davis-Besse Nuclear Power Station2023-12-0707 December 2023 Corrections to the 2022 Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report for the Davis-Besse Nuclear Power Station ML23338A3172023-12-0606 December 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000346/2024001 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 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 ML23269A1242023-09-27027 September 2023 Request for Withholding Information from Public Disclosure 2024-09-06
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARL-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 L-23-048, Response to Request for Additional Information Regarding Technical Specification 5.6.6 Steam Generator Tube Inspection 180-Day Report2023-03-0101 March 2023 Response to Request for Additional Information Regarding Technical Specification 5.6.6 Steam Generator Tube Inspection 180-Day Report ML22292A0232022-10-18018 October 2022 Framatome Inc., Document ANP-2718-007Q1NP, Revision 0, Response to Request for Additional Information on Appendix G Pressure-Temperature Limits for 52 EFPY for Davis-Besse Nuclear Power Station - First Energy Nuclear Operating Company L-22-229, Response to Request for Additional Information Regarding Request to Withhold Information in Framatome Inc. Document ANP-2718P-007 from Public Disclosure & Affidavit2022-10-13013 October 2022 Response to Request for Additional Information Regarding Request to Withhold Information in Framatome Inc. Document ANP-2718P-007 from Public Disclosure & Affidavit L-22-152, Response to Request for Additional Information Regarding a License Amendment Request That Revises the Davis-Besse Nuclear Power Station Emergency Plan2022-07-0505 July 2022 Response to Request for Additional Information Regarding a License Amendment Request That Revises the Davis-Besse Nuclear Power Station Emergency Plan L-22-124, Response to Request for Additional Information Regarding License Amendment Request to Revise the Design Basis for the Shield Building2022-05-12012 May 2022 Response to Request for Additional Information Regarding License Amendment Request to Revise the Design Basis for the Shield Building L-22-059, Response to Request for Additional Information on Proposed Inservice Test Alternative RP-32022-03-21021 March 2022 Response to Request for Additional Information on Proposed Inservice Test Alternative RP-3 ML22081A1472022-03-11011 March 2022 R22 (March 2022) - Steam Generator Tube Inspection Discussion Points 11 March 2022 ML22049A0662022-02-10010 February 2022 Response to NRC Questions from 2/1/2022 Regulatory Conference on Failed Field Flash Selector Switch L-21-266, Response to Request for Additional Information on Proposed Inservice Inspection Alternative RR-A22022-01-27027 January 2022 Response to Request for Additional Information on Proposed Inservice Inspection Alternative RR-A2 ML21130A2192021-05-10010 May 2021 Request for Additional Information Regarding Steam Generator Tube Inspection Reports (EPIDs L2020-LRO-0055, L-2020-LRO-0082, and L2020-LRO-0083) L-21-101, Final Supplemental Response to Nuclear Regulatory Commission Generic Letter 2004-022021-03-29029 March 2021 Final Supplemental Response to Nuclear Regulatory Commission Generic Letter 2004-02 ML21088A3442021-03-29029 March 2021 Final Supplemental Response to Nuclear Regulatory Commission Generic Letter 2004-02 L-21-030, Response to Request for Additional Information Regarding an Amendment to Incorporate the Applicable Standard Technical Specification 5.2.2, Unit Staff, Into the Facility Technical Specifications (EPID L-20202021-01-27027 January 2021 Response to Request for Additional Information Regarding an Amendment to Incorporate the Applicable Standard Technical Specification 5.2.2, Unit Staff, Into the Facility Technical Specifications (EPID L-2020 L-20-313, Response to Request for Additional Information Regarding Request for Exemption -Part 73 Force-on-Force2020-12-0707 December 2020 Response to Request for Additional Information Regarding Request for Exemption -Part 73 Force-on-Force L-20-183, Response to Request for Additional Information Regarding License Amendment Request for Adoption of TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control - Risk Informed Technical Specification Task Force2020-06-23023 June 2020 Response to Request for Additional Information Regarding License Amendment Request for Adoption of TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control - Risk Informed Technical Specification Task Force L-20-155, Response to Request for Additional Information Regarding Request for Exemptions to Certain Periodic Training Requirements for Security Personnel (Epids L-2020-LLE-0026 to -0040)2020-05-0606 May 2020 Response to Request for Additional Information Regarding Request for Exemptions to Certain Periodic Training Requirements for Security Personnel (Epids L-2020-LLE-0026 to -0040) L-20-041, Response to Request for Additional Information Regarding License Amendment Request to Extend Containment Leakage Test Interval2020-02-0303 February 2020 Response to Request for Additional Information Regarding License Amendment Request to Extend Containment Leakage Test Interval L-19-182, Response to RAI Regarding an Application for Order Consenting to Transfer of License2019-08-0202 August 2019 Response to RAI Regarding an Application for Order Consenting to Transfer of License L-19-178, Response to Request for Additional Information Regarding Request for Approval of Decommissioning Quality Assurance Program for the Davis-Besse Nuclear Power Station2019-07-16016 July 2019 Response to Request for Additional Information Regarding Request for Approval of Decommissioning Quality Assurance Program for the Davis-Besse Nuclear Power Station L-19-166, Response to Request for Additional Information and Supplemental Information Regarding License Amendment Request for Proposed Post-Shutdown Emergency Plan2019-07-0808 July 2019 Response to Request for Additional Information and Supplemental Information Regarding License Amendment Request for Proposed Post-Shutdown Emergency Plan L-19-160, Response to Request for Additional Information Regarding License Amendment Request for Permanently Defueled Technical Specifications2019-06-26026 June 2019 Response to Request for Additional Information Regarding License Amendment Request for Permanently Defueled Technical Specifications L-18-121, Response to Request for Supplemental Information Regarding Generic Letter 2016-01 Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools.2018-05-25025 May 2018 Response to Request for Supplemental Information Regarding Generic Letter 2016-01 Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools. L-18-125, Response to Follow-up Request for Additional Information Regarding Exemption Request for a Physical Barrier Requirement IEPID-L-2017-l-LE-0019 (CAC Nos.000976/05000334/-L-2017-LLE-0019 MG0010, 000976/05000334/L-2017-LLE-0019 MG0011,000976/02018-05-0202 May 2018 Response to Follow-up Request for Additional Information Regarding Exemption Request for a Physical Barrier Requirement IEPID-L-2017-l-LE-0019 (CAC Nos.000976/05000334/-L-2017-LLE-0019 MG0010, 000976/05000334/L-2017-LLE-0019 MG0011,000976/0 L-18-085, Response to Request for Additional Information and Supplemental Information Regarding License Amendment Request to Adopt National Fire Protection Association (NFPA) Standard 8052018-04-0202 April 2018 Response to Request for Additional Information and Supplemental Information Regarding License Amendment Request to Adopt National Fire Protection Association (NFPA) Standard 805 L-18-061, Units. 1 & 2, Davis-Besse, and Perry, Response to Request for Additional Information Regarding Exemption Request for a Physical Barrier Requirement2018-03-16016 March 2018 Units. 1 & 2, Davis-Besse, and Perry, Response to Request for Additional Information Regarding Exemption Request for a Physical Barrier Requirement L-17-372, Response to Request for Additional Information Regarding Request to Use ASME Code Case N-513-4 (EPID 000976/05000334/L-2017-LLR-0088,000976/05000346/L-2017-LLR-0088, 000976/05000412/L-2017-LLR-0088, and 000976/05000440/L-2017-LLR-0088)2017-12-23023 December 2017 Response to Request for Additional Information Regarding Request to Use ASME Code Case N-513-4 (EPID 000976/05000334/L-2017-LLR-0088,000976/05000346/L-2017-LLR-0088, 000976/05000412/L-2017-LLR-0088, and 000976/05000440/L-2017-LLR-0088) L-17-253, Supplemental Information Regarding License Amendment Request to Adopt National Fire Protection Association (NFPA) Standard 8052017-10-0909 October 2017 Supplemental Information Regarding License Amendment Request to Adopt National Fire Protection Association (NFPA) Standard 805 L-17-233, High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information, Per 10CFR50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force (NTTF) Review of Insights from the Fukishima Dai-ichi Accident2017-08-0202 August 2017 High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information, Per 10CFR50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force (NTTF) Review of Insights from the Fukishima Dai-ichi Accident L-17-189, Response to Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association (NFPA) Standard 8052017-06-16016 June 2017 Response to Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association (NFPA) Standard 805 ML17163A4122017-06-0808 June 2017 Areva, ANP-3542Q1NP, Revision 0, Response to NRC Request for Additional Information on Time-Limited Aging Analysis for the DB-1 Reactor Vessel Internals. L-17-158, Reply to Request for Additional Information Re License Renewal Commitment No. 422017-05-12012 May 2017 Reply to Request for Additional Information Re License Renewal Commitment No. 42 L-17-070, Reply to Request for Additional Information Related to License Renewal Commitment2017-02-22022 February 2017 Reply to Request for Additional Information Related to License Renewal Commitment L-16-371, Response to Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association (NFPA) Standard 8052017-01-17017 January 2017 Response to Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association (NFPA) Standard 805 L-16-345, Response to Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Cnfpa) Standard 8052016-12-16016 December 2016 Response to Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Cnfpa) Standard 805 L-16-323, Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Pursuant to CFR 50.54(f) Regarding Recommendation 2.1 of the Near Term Task Force Review of Insights from Fukushima Dai-inchi Accident2016-12-0909 December 2016 Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Pursuant to CFR 50.54(f) Regarding Recommendation 2.1 of the Near Term Task Force Review of Insights from Fukushima Dai-inchi Accident L-16-291, Response to Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools2016-11-0101 November 2016 Response to Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools L-16-279, Reply to Request for Additional Information Related to License Renewal Commitment 422016-09-26026 September 2016 Reply to Request for Additional Information Related to License Renewal Commitment 42 L-16-123, Completion of Required Action by NRC Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events2016-09-23023 September 2016 Completion of Required Action by NRC Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events L-16-256, Response to Request for Additional Information Regarding a Request to Revise the Emergency Plan2016-09-0606 September 2016 Response to Request for Additional Information Regarding a Request to Revise the Emergency Plan L-16-220, Response to Regulatory Issue Summary 2016-09, Preparation and Scheduling of Operator Licensing Examinations.2016-07-20020 July 2016 Response to Regulatory Issue Summary 2016-09, Preparation and Scheduling of Operator Licensing Examinations. L-16-085, Request for Additional Information Response Related to Modification of Technical Specification 5.3.1, Unit Staff Qualifications.2016-03-22022 March 2016 Request for Additional Information Response Related to Modification of Technical Specification 5.3.1, Unit Staff Qualifications. L-16-079, Supplemental Information for License Amendment Request to Adopt National Fire Protection Association (NFPA) Standard 8052016-03-0707 March 2016 Supplemental Information for License Amendment Request to Adopt National Fire Protection Association (NFPA) Standard 805 L-16-040, Response to Request for Additional Information Regarding License Amendment Request to Revise Emergency Diesel Generator Minimum Voltage and Frequency Surveillance Requirements2016-02-19019 February 2016 Response to Request for Additional Information Regarding License Amendment Request to Revise Emergency Diesel Generator Minimum Voltage and Frequency Surveillance Requirements ML15299A1432015-10-19019 October 2015 Additional Information for the Advisory Committee on Reactor Safeaquards Review of the License Renewal Application, Including Enclosure a, Bechtel Affidavit L-15-268, Response to Request for Additional Information Regarding License Amendment Request to Revise Emergency Diesel Generator Minimum Voltage and Frequency Surveillance Requirements2015-10-14014 October 2015 Response to Request for Additional Information Regarding License Amendment Request to Revise Emergency Diesel Generator Minimum Voltage and Frequency Surveillance Requirements ML15280A2872015-10-0606 October 2015 Additional Information for the Advisory Committee on Reactor Safeguards Review of License Renewal Application L-15-263, Response to Request for Additional Information Related to Security Plan Changes2015-08-17017 August 2015 Response to Request for Additional Information Related to Security Plan Changes L-15-197, Response to Request for Additional Information Regarding a Request to Amend Technical Specification 5.5.15. Containment Leakage Rate Testing Program2015-06-26026 June 2015 Response to Request for Additional Information Regarding a Request to Amend Technical Specification 5.5.15. Containment Leakage Rate Testing Program 2024-08-15
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in accordance with 10 CFR 2.390_______ Upon .removal of Enclosure C, this letter can be decontrolled.
50 ot tt ot First Energy Nuclear Operating Company Oak Harbor, Ohio 43449 Brian D. Boles 419-321-7676 Vice President, Fax: 419-321-7582 Nuclear October 19, 2015-L-1 5-328 10 CFR 54 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
SUBJECT:
Davis-Besse Nuclear Power Station, Unit No. I Docket No. 50-346, License Number NPF-3 Additional Information for the Advisory Committee on Reactor Safeaquards Review of the Davis-Besse..Nuclear Power Station. Unit No. 1. License Renewal Application (TAC No. ME4640)By letter dated August 27, 2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML1 02450565), FirstEnergy Nuclear Operating Company (FENOC) submitted an application pursuant to Title 10 of the Code of Federal Regulations, Part 54 for renewal of Operating License NPF-3 for the Davis-Besse Nuclear Power Station, Unit No. 1 (Davis-Besse).
Following the September 23, 2015 meeting between FENOC and the Advisory Committee on Reactor Safeguards (ACRS)License Renewal Subcommittee, the members requested additional information to clarify statements made by FENOC during the meeting and to complete their review of the License Renewal Application (LRA).The following information is provided to clarify the ACRS Subcommittee meeting discussion regarding the Davis-Besse Shield Building crack propagation margin statements.
The 100-foot crack propagation margin value was derived using Shield Building Region 4 margin value in percent of area cracked (i.e., 20% margin) multiplied by the circumference of the Shield Building (i.e., 452 feet), which results in: "0.20 x 452 feet = approximately 100 feet The supplemental information provided by FENOC letter dated October 6, 2015 (ML15280A287), provides a more detailed description regarding the determination of the area for crack propagation margin, and is accompanied by a figure. The description in that letter focuses on crack propagation from leading edges and expresses crack propagation margin in years based on the current observed crack growth rate.
Davis-Besse Nuclear Power Station, Unit No. 1 L-1 5-328 Page 2 The Enclosures listed below provide the requested Davis-Besse Shield Building reinforcing bar (rebar) splice capacity report from Bechtel Power Corporation (Bechtel), which includes the results of testing studies at Purdue University and the University of Kansas: A. Bechtel Affidavit to Support the Disclosure Request for the Proprietary Splice Capacity Report B. Bechtel Report No. 25593-000-G83-GEG-00016-000, "Effect of Laminar Cracks on Splice Capacity of No. 11 Bars based on Testing Conducted at Purdue University anid University of Kansas for Davis-Besse Shield Building" (Non-Proprietary)
C. Bechtel Report No. 25593-000-G83-GEG-00016-000, "Effect of Laminar Cracks on Splice Capacity of No. 11 Bars based on Testing Conducted at Purdue University and University of Kansas for Davis-Besse Shield Building" (Proprietary)
Bechtel Report No. 25593-000-G83-GEG-00016-000 (Enclosure C) documents Davis-Besse Shield Building rebar splice capacity analysis details that are considered proprietary information that is to be withheld from public disclosure pursuant to 10 CFR 2.390. A non-proprietary version of the document is provided as Enclosure B.Upon removal of Enclosure C, this letter can be decontrolled.
There are no regulatory commitments contained in this letter. If there are any questions or if additional information is required, please contact Mr. Clifford I. Custer, Fleet License Renewal Project Manager, at 724-682-7139.
I declare under penalty of perjury that the foregoing is true and correct. Executed on October /9i , 2015.Sincerely, Brian D. Boles Davis-Besse Nuclear Power Station, Unit No. 1 L-1 5-328 Page 3
Enclosures:
A. Bechtel Affidavit to Support the Disclosure Request for the Proprietary Splice Capacity Report B. Bechtel Report No. 25593-000-G83-GEG-00016-000, "Effect of Laminar Cracks on Splice Capacity of No. 11 Bars based on Testing Conducted at Purdue University and University of Kansas for Davis-Besse Shield Building" (Non Proprietary)
C. Bechtel Report No. 25593-000-G83-GEG-00016-000, "Effect of Laminar Cracks on Splice Capacity of No. 11 Bars based on Testing Conducted at Purdue University and University of Kansas for Davis-Besse Shield Building" (Proprietary) cc: w/o Enclosures NRC DLR Project Manager NRC Region Ill Administrator NRC DLR Director NRR DORL Project Manager NRC Resident Inspector Utility Radiological Safety Board Enclosure A Davis-Besse Nuclear Power Station, Unit No. 1 (Davis-Besse)
Letter L-15-328 Bechtel Affidavit to Suppnort the Disclosure Reauest for the Proprietary Splice Capacity Report 3 pages follow 10 CFR 2.390 AFFIDAVIT OF STEPHEN D. ROUTH SUPPORTING APPLICATION TO WITHHOLD FROM PUBLIC DISCLOSURE BECHTEL REPORT 25593-000-G83-00016-O0,0"EFFECT OF LAMINAR CRACKS ON SPLICE CAPACITY OF NO. 11 BARS BASED ON TESTING CONDUCTED AT PURDUE UNIVERSITY AND UNIVERSITY OF KANSAS FOR DAVISE-BESSE SHIELD BUILDING," July 30, 2012 I, Stephen 0. Routh, Manager of Nuclear Engineering Services, of Bechtel Power Corporation (Bechtel), having been duly sworn, do hereby affirm and state: I have been authorized by Bechtel to (a) review the Information owned by Bechtel which is referenced herein relating to supporting analyses for the Davis-Besse Nuclear Power Station which Bechtel seeks to have withheld from public disclosure pursuant to 10 CFR 2.390(a)(4), and (b) apply for the withholding of such information from public disclosure by the Nuclear Regulatory Commission (NRC) on behalf of Bechtel.1. Pursuant to the provisions of 10 CFR 2.390(b)(3), the following is furnished for consideration by the Commission in determining whether the information sought to be withheld from public disclosure should be withheld.i. The information sought to be withheld from public disclosure is owned and has been held in confidence by Bechtel.ii. The information Is of a type customarily held in confidence by Bechtel and not customarily disclosed to the public. Bechtel has a rational basis for determining the types of information customadily held in confidence by it and, in that connection, utilizes a system to determine when and whether to hold certain types of information in confidence.
The application of that system and the substance of that system constitute Bechtel policy and provide the rational basis required.Under that system, information is held in confidence if it falls in one or more of several types, the release of which might result in the loss of an existing or potential competitive advantage, as follows: a) The information reveals the distinguishing aspects of a process (or component, structure, tool, method, etc.) where presentation of its use by any of Bechtel's competitors without license from Bechtel constitutes a competitive economic advantage.
b) It consists of supporting data, including test data, relative to a process (or component, structure, tool, method, etc.), the application of which data secures a competitive economic advantage (e.g., by optimization or improved marketability).
c) Its use by a competitor Would reduce their expenditure of resources or improve their competitive position in the design, manufacture, shipment, installation, assurance of quality, or licensing a similar product.
d) It reveals cost or price information, production capacities, budget levels, or commercial strategies of Bechtel, its customers; or suppliers.
e) It reveals aspects of past, present, or future Bechtel or customer funded development plans and programs of potential commercial value to Bechtel.f) It contains patentable ideas, for which patent protection may be desirable.
There are sound policy reasons behind the Bechtel system which inciude the following:
a) The use of such information by Bechtel gives Bechtel a competitive advantage over its competitors.
It is, therefore, withheld from disclosure to protect the Bechtel competitive position.b) It is information, which is marketable in many ways. The extent to which such information is available to competitors diminishes Bechtel's ability to sell products and services involving the use of the information.
c) Use by our competitors would put Bechtel at a competitive disadvantage by reducing their expenditure of resources at Bechtel expense.d) Each component of proprietary information pertinent to a particular competitive advantage is potentially as valuable as the total competitive advantage.
If competitors acquire components or proprietary information, anyone component may be the key to the entire puzzle, thereby depriving Bechtel of a competitive advantage.
e) Unrestricted disclosure would jeopardize the position of prominence of Bechtel in the world market, and thereby give a market advantage to the competition.
f) The Bechtel capacity to invest corporate assets in research and development depends upon the success in obtaining and maintaining a competitive advantage.
iii. The information is being transmitted to the Commission in confidence and, under the provisions of 10 CFR 2.390, it is to be received in confidence by the Commission.
iv. The information sought to be protected is not available in public sources or available information has not been previously employed in the same original manner or method to the best of our knowledge and belief.v. The proprietary information specifically sought to be withheld is Bechtel Report 25593-000-G83-GEG-0001 6-000, "Effect of Laminar Cracks on Splice Capacity of No. 11 Bars based on Testing Conducted at Purdue University and University of Kansas for Davis-Besse Shield Building," which was prepared to support evaluations of cracks found in the Davis-Besse concrete Shield Building.
This report was prepared by Bechtel to analyze the potential effects of the concrete cracks on the structural integrity of the concrete Shield Building.Public disclosure of this proprietary information is likely to cause substantial harm to the competitive position of Bechtel because it would enhance the ability of competitors to perform similar evaluations and related services for commercial power reactors without commensurate expenses.
Also, public disclosure of the information would enable others to use the Information to meet NRC requirements for licensing documentation without purchasing the right to use the information.
The development of the information described in part is the result of applying the results of many analyst-hours and significant monetary expenditure.
In order for a competitor of Bechtel to duplicate this information, similar evaluations would have to be performed and a significant manpower effort, having the requisite talent and experience, would have to be expended.Further affiant sayeth not.Stephen D. Routh, having been duly sworn, hereby confirms that i am the Manager of Nuclear Engineering Services, of Bechtel Power Corporation, that I am authorized on behalf of Bechtel to review the information attached hereto and to sign and file with the Nuclear Regulatory Commission this affidavit and the attachments hereto, and that the statements made and matters set forth herein are true and correct to the best of my knowledge, information, and belief.Stephen D. Routh On this day of .2015, he individual signing above personally appeared before me, is known by me to be the person whose name is subscribed to within the instrument, and acknowledged that he executed the same for the purposes therein contained.
In witness hereof I hereunto set my hand and official seal.Notar Public
- r 'Steof Maryland Notary Public 14 resdmeric.SCoutey
,21 State of Maryland, Frederick County My OImIS~N xpSepeibu 1 2i8 My commission expires //=(/
in accordance with 10 CFR 2.390_______ Upon .removal of Enclosure C, this letter can be decontrolled.
50 ot tt ot First Energy Nuclear Operating Company Oak Harbor, Ohio 43449 Brian D. Boles 419-321-7676 Vice President, Fax: 419-321-7582 Nuclear October 19, 2015-L-1 5-328 10 CFR 54 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
SUBJECT:
Davis-Besse Nuclear Power Station, Unit No. I Docket No. 50-346, License Number NPF-3 Additional Information for the Advisory Committee on Reactor Safeaquards Review of the Davis-Besse..Nuclear Power Station. Unit No. 1. License Renewal Application (TAC No. ME4640)By letter dated August 27, 2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML1 02450565), FirstEnergy Nuclear Operating Company (FENOC) submitted an application pursuant to Title 10 of the Code of Federal Regulations, Part 54 for renewal of Operating License NPF-3 for the Davis-Besse Nuclear Power Station, Unit No. 1 (Davis-Besse).
Following the September 23, 2015 meeting between FENOC and the Advisory Committee on Reactor Safeguards (ACRS)License Renewal Subcommittee, the members requested additional information to clarify statements made by FENOC during the meeting and to complete their review of the License Renewal Application (LRA).The following information is provided to clarify the ACRS Subcommittee meeting discussion regarding the Davis-Besse Shield Building crack propagation margin statements.
The 100-foot crack propagation margin value was derived using Shield Building Region 4 margin value in percent of area cracked (i.e., 20% margin) multiplied by the circumference of the Shield Building (i.e., 452 feet), which results in: "0.20 x 452 feet = approximately 100 feet The supplemental information provided by FENOC letter dated October 6, 2015 (ML15280A287), provides a more detailed description regarding the determination of the area for crack propagation margin, and is accompanied by a figure. The description in that letter focuses on crack propagation from leading edges and expresses crack propagation margin in years based on the current observed crack growth rate.
Davis-Besse Nuclear Power Station, Unit No. 1 L-1 5-328 Page 2 The Enclosures listed below provide the requested Davis-Besse Shield Building reinforcing bar (rebar) splice capacity report from Bechtel Power Corporation (Bechtel), which includes the results of testing studies at Purdue University and the University of Kansas: A. Bechtel Affidavit to Support the Disclosure Request for the Proprietary Splice Capacity Report B. Bechtel Report No. 25593-000-G83-GEG-00016-000, "Effect of Laminar Cracks on Splice Capacity of No. 11 Bars based on Testing Conducted at Purdue University anid University of Kansas for Davis-Besse Shield Building" (Non-Proprietary)
C. Bechtel Report No. 25593-000-G83-GEG-00016-000, "Effect of Laminar Cracks on Splice Capacity of No. 11 Bars based on Testing Conducted at Purdue University and University of Kansas for Davis-Besse Shield Building" (Proprietary)
Bechtel Report No. 25593-000-G83-GEG-00016-000 (Enclosure C) documents Davis-Besse Shield Building rebar splice capacity analysis details that are considered proprietary information that is to be withheld from public disclosure pursuant to 10 CFR 2.390. A non-proprietary version of the document is provided as Enclosure B.Upon removal of Enclosure C, this letter can be decontrolled.
There are no regulatory commitments contained in this letter. If there are any questions or if additional information is required, please contact Mr. Clifford I. Custer, Fleet License Renewal Project Manager, at 724-682-7139.
I declare under penalty of perjury that the foregoing is true and correct. Executed on October /9i , 2015.Sincerely, Brian D. Boles Davis-Besse Nuclear Power Station, Unit No. 1 L-1 5-328 Page 3
Enclosures:
A. Bechtel Affidavit to Support the Disclosure Request for the Proprietary Splice Capacity Report B. Bechtel Report No. 25593-000-G83-GEG-00016-000, "Effect of Laminar Cracks on Splice Capacity of No. 11 Bars based on Testing Conducted at Purdue University and University of Kansas for Davis-Besse Shield Building" (Non Proprietary)
C. Bechtel Report No. 25593-000-G83-GEG-00016-000, "Effect of Laminar Cracks on Splice Capacity of No. 11 Bars based on Testing Conducted at Purdue University and University of Kansas for Davis-Besse Shield Building" (Proprietary) cc: w/o Enclosures NRC DLR Project Manager NRC Region Ill Administrator NRC DLR Director NRR DORL Project Manager NRC Resident Inspector Utility Radiological Safety Board Enclosure A Davis-Besse Nuclear Power Station, Unit No. 1 (Davis-Besse)
Letter L-15-328 Bechtel Affidavit to Suppnort the Disclosure Reauest for the Proprietary Splice Capacity Report 3 pages follow 10 CFR 2.390 AFFIDAVIT OF STEPHEN D. ROUTH SUPPORTING APPLICATION TO WITHHOLD FROM PUBLIC DISCLOSURE BECHTEL REPORT 25593-000-G83-00016-O0,0"EFFECT OF LAMINAR CRACKS ON SPLICE CAPACITY OF NO. 11 BARS BASED ON TESTING CONDUCTED AT PURDUE UNIVERSITY AND UNIVERSITY OF KANSAS FOR DAVISE-BESSE SHIELD BUILDING," July 30, 2012 I, Stephen 0. Routh, Manager of Nuclear Engineering Services, of Bechtel Power Corporation (Bechtel), having been duly sworn, do hereby affirm and state: I have been authorized by Bechtel to (a) review the Information owned by Bechtel which is referenced herein relating to supporting analyses for the Davis-Besse Nuclear Power Station which Bechtel seeks to have withheld from public disclosure pursuant to 10 CFR 2.390(a)(4), and (b) apply for the withholding of such information from public disclosure by the Nuclear Regulatory Commission (NRC) on behalf of Bechtel.1. Pursuant to the provisions of 10 CFR 2.390(b)(3), the following is furnished for consideration by the Commission in determining whether the information sought to be withheld from public disclosure should be withheld.i. The information sought to be withheld from public disclosure is owned and has been held in confidence by Bechtel.ii. The information Is of a type customarily held in confidence by Bechtel and not customarily disclosed to the public. Bechtel has a rational basis for determining the types of information customadily held in confidence by it and, in that connection, utilizes a system to determine when and whether to hold certain types of information in confidence.
The application of that system and the substance of that system constitute Bechtel policy and provide the rational basis required.Under that system, information is held in confidence if it falls in one or more of several types, the release of which might result in the loss of an existing or potential competitive advantage, as follows: a) The information reveals the distinguishing aspects of a process (or component, structure, tool, method, etc.) where presentation of its use by any of Bechtel's competitors without license from Bechtel constitutes a competitive economic advantage.
b) It consists of supporting data, including test data, relative to a process (or component, structure, tool, method, etc.), the application of which data secures a competitive economic advantage (e.g., by optimization or improved marketability).
c) Its use by a competitor Would reduce their expenditure of resources or improve their competitive position in the design, manufacture, shipment, installation, assurance of quality, or licensing a similar product.
d) It reveals cost or price information, production capacities, budget levels, or commercial strategies of Bechtel, its customers; or suppliers.
e) It reveals aspects of past, present, or future Bechtel or customer funded development plans and programs of potential commercial value to Bechtel.f) It contains patentable ideas, for which patent protection may be desirable.
There are sound policy reasons behind the Bechtel system which inciude the following:
a) The use of such information by Bechtel gives Bechtel a competitive advantage over its competitors.
It is, therefore, withheld from disclosure to protect the Bechtel competitive position.b) It is information, which is marketable in many ways. The extent to which such information is available to competitors diminishes Bechtel's ability to sell products and services involving the use of the information.
c) Use by our competitors would put Bechtel at a competitive disadvantage by reducing their expenditure of resources at Bechtel expense.d) Each component of proprietary information pertinent to a particular competitive advantage is potentially as valuable as the total competitive advantage.
If competitors acquire components or proprietary information, anyone component may be the key to the entire puzzle, thereby depriving Bechtel of a competitive advantage.
e) Unrestricted disclosure would jeopardize the position of prominence of Bechtel in the world market, and thereby give a market advantage to the competition.
f) The Bechtel capacity to invest corporate assets in research and development depends upon the success in obtaining and maintaining a competitive advantage.
iii. The information is being transmitted to the Commission in confidence and, under the provisions of 10 CFR 2.390, it is to be received in confidence by the Commission.
iv. The information sought to be protected is not available in public sources or available information has not been previously employed in the same original manner or method to the best of our knowledge and belief.v. The proprietary information specifically sought to be withheld is Bechtel Report 25593-000-G83-GEG-0001 6-000, "Effect of Laminar Cracks on Splice Capacity of No. 11 Bars based on Testing Conducted at Purdue University and University of Kansas for Davis-Besse Shield Building," which was prepared to support evaluations of cracks found in the Davis-Besse concrete Shield Building.
This report was prepared by Bechtel to analyze the potential effects of the concrete cracks on the structural integrity of the concrete Shield Building.Public disclosure of this proprietary information is likely to cause substantial harm to the competitive position of Bechtel because it would enhance the ability of competitors to perform similar evaluations and related services for commercial power reactors without commensurate expenses.
Also, public disclosure of the information would enable others to use the Information to meet NRC requirements for licensing documentation without purchasing the right to use the information.
The development of the information described in part is the result of applying the results of many analyst-hours and significant monetary expenditure.
In order for a competitor of Bechtel to duplicate this information, similar evaluations would have to be performed and a significant manpower effort, having the requisite talent and experience, would have to be expended.Further affiant sayeth not.Stephen D. Routh, having been duly sworn, hereby confirms that i am the Manager of Nuclear Engineering Services, of Bechtel Power Corporation, that I am authorized on behalf of Bechtel to review the information attached hereto and to sign and file with the Nuclear Regulatory Commission this affidavit and the attachments hereto, and that the statements made and matters set forth herein are true and correct to the best of my knowledge, information, and belief.Stephen D. Routh On this day of .2015, he individual signing above personally appeared before me, is known by me to be the person whose name is subscribed to within the instrument, and acknowledged that he executed the same for the purposes therein contained.
In witness hereof I hereunto set my hand and official seal.Notar Public
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