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MONTHYEARML11193A0932011-05-27027 May 2011 Reply to RAI for the Review of the Davis-Besse Nuclear Power Station, Unit 1, License Renewal Application Environmental Report and Enclosure a - Environmental Audit Needs List Project stage: Other ML1108202762011-06-0303 June 2011 Summary of Site Audit Related to the Review of the License Renewal Application for Davis-Besse Nuclear Power Station, Unit 1 Project stage: Approval L-11-154, Reply to Request for Additional Information for the Review of License Renewal Application, Environmental Report Severe Accident Mitigation Alternatives Analysis, and License Renewal Application Amendment No. 102011-06-24024 June 2011 Reply to Request for Additional Information for the Review of License Renewal Application, Environmental Report Severe Accident Mitigation Alternatives Analysis, and License Renewal Application Amendment No. 10 Project stage: Response to RAI L-11-222, Ohio Department of Natural Resources Office of Coastal Management Concurrence with Federal Consistency Certification Related to the Review of License Renewal Application Environmental Report2011-07-11011 July 2011 Ohio Department of Natural Resources Office of Coastal Management Concurrence with Federal Consistency Certification Related to the Review of License Renewal Application Environmental Report Project stage: Other ML1122701392011-08-15015 August 2011 Request for Additional Information Response Clarification from Davis-Besse Nuclear Power Station in Support of License Renewal Application Review Project stage: RAI L-11-251, Reply to Supplemental Request for Additional Information for Review of License Renewal Application, Environmental Report Severe Accident Mitigation Alternatives Analysis2011-09-0101 September 2011 Reply to Supplemental Request for Additional Information for Review of License Renewal Application, Environmental Report Severe Accident Mitigation Alternatives Analysis Project stage: Supplement L-11-288, License Renewal Application Amendment No. 17, Supplemental Information for Environmental Report2011-09-19019 September 2011 License Renewal Application Amendment No. 17, Supplemental Information for Environmental Report Project stage: Supplement L-11-289, License Renewal Application Amendment No. 16, Supplemental Information for the Review of the License Renewal Application Environmental Report2011-09-19019 September 2011 License Renewal Application Amendment No. 16, Supplemental Information for the Review of the License Renewal Application Environmental Report Project stage: Supplement ML12032A1312012-01-31031 January 2012 Schedule Revision for the Environmental Review of the Davis-Besse Nuclear Power Station, Unit No. 1, LRA Project stage: Approval ML12025A1092012-01-31031 January 2012 Schedule Revision for the Environmental Review of the Davis-Besse Nuclear Power Station, Unit No. 1, License Renewal Application Project stage: Approval L-12-244, Correction of Errors in the License Renewal Application Environmental Report Severe Accident Mitigation Alternatives Analysis, and License Renewal Application Amendment No. 292012-07-16016 July 2012 Correction of Errors in the License Renewal Application Environmental Report Severe Accident Mitigation Alternatives Analysis, and License Renewal Application Amendment No. 29 Project stage: Other ML13205A0362013-07-31031 July 2013 Schedule Revision for the Environmental and Safety Review of the Davis-Besse Nuclear Power Station License Renewal Application (TAC Nos. ME4613 and ME4640) Project stage: Approval ML13302C2072013-11-0606 November 2013 Schedule Revision for the Review of the Davis-Besse Nuclear Power Station License Renewal Application (TAC ME4613 and ME4640) Project stage: Approval ML14027A2172014-01-30030 January 2014 Schedule Revision for Environmental Review of Davis-Besse Nuclear Power Station License Renewal Application Project stage: Approval ML14097A2722014-03-25025 March 2014 Slides for Davis-Besse Draft SEIS for License Renewal Public Meeting - Preliminary Site-Specific Results of the License Renewal Environmental Review for Davis-Besse Nuclear Power Station, March 25, 2014 Project stage: Draft Approval ML14097A2532014-03-25025 March 2014 Transcript of 03/25/2014 for Davis-Besse Nuclear Power Station Draft Environmental Impact Statement Public Meeting: Evening Session - Corrected. Pages 1-84 Project stage: Request ML14097A2542014-03-25025 March 2014 Draft Environmental Impact Statement Public Meeting: Afternoon Session - Corrected. Pages 1-56 Project stage: Request ML14112A3152014-04-21021 April 2014 Review of Draft Plant-Specific Supplement 52 to the Generic Environmental Impact Statement for License Renewal of Nuclear Plants Regarding ML14099A3392014-04-22022 April 2014 March 27, 2014, Summary of Telephone Conference Call Held Between Nuclear Regulatory Commission and First Energy Nuclear Operating Company Concerning Commitment 13 of the Safety Evaluation Report Pertaining to the Davis Besse Unit 1, Licens Project stage: Request ML14099A4642014-05-0606 May 2014 Summary of Public Meetings to Discuss Draft Supplement 52 to the Generic Environmental Impact Statement for License Renewal of Nuclear Plants Regarding Davis-Besse Nuclear Generating Station, Unit 1 L-14-206, License Renewal Application Amendment No. 50 - Annual Update2014-06-23023 June 2014 License Renewal Application Amendment No. 50 - Annual Update Project stage: Other ML14329A4792014-11-28028 November 2014 Schedule Revision for the Review of the Davis-Besse Nuclear Power Station License Renewal Application (TAC No. ME613) Project stage: Approval ML15054A5342015-02-27027 February 2015 Schedule Revision and Project Manager Change for the Review of the Davis-Besse Nuclear Power Station License Renewal Application Project stage: Approval ML15113A1072015-04-30030 April 2015 Schedule Revision for the Review of the Davis-Besse Nuclear Power Station License Renewal Application Project stage: Approval 2013-11-06
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Category:Letter
MONTHYEARIR 05000346/20244032024-09-27027 September 2024 Security Baseline Inspection Report 05000346/2024403 L-24-025, Submittal of the Updated Final Safety Analysis Report, Revision 352024-09-25025 September 2024 Submittal of the Updated Final Safety Analysis Report, Revision 35 05000346/LER-2021-001, 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 IR 05000346/20234012023-09-13013 September 2023 Security Baseline Inspection Report 05000346/2023401 (Public) 2024-09-06
[Table view] Category:Report
MONTHYEARL-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-23-188, Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-08-0707 August 2023 Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments L-22-253, Submittal of Pressure and Temperature Limits Report, Revision 52023-01-10010 January 2023 Submittal of Pressure and Temperature Limits Report, Revision 5 L-22-211, Technical Specification 5.6.6 Steam Generator Tube Inspection 180-Day Report2022-09-29029 September 2022 Technical Specification 5.6.6 Steam Generator Tube Inspection 180-Day Report L-22-216, Submittal of Pressure and Temperature Limits Report. Revision 42022-09-27027 September 2022 Submittal of Pressure and Temperature Limits Report. Revision 4 L-22-149, Post Accident Monitoring Report2022-06-23023 June 2022 Post Accident Monitoring Report ML22202A4362022-04-0808 April 2022 Enclosure F: Updated Inputs to 52 EFPY P-T Operating Curves ML22202A4372022-03-0202 March 2022 Enclosure G: Framatome Inc. Document 86-9344713-000, Davis-Besse Reactor Vessel Embrittlement Fluence Reconciliation Through 60 Years IR 05000346/20210902021-12-16016 December 2021 Reissue Davis-Besse NRC Inspection Report (05000346/2021090) Preliminary White Finding ML21322A2892021-12-0909 December 2021 Approval of Plant-Specific Analysis of Certain Reactor Vessel Internal Components in Accordance with License Renewal Commitment No. 53 ML20302A3022020-09-25025 September 2020 1 to Technical Requirements Manual ML19255H0992019-10-10010 October 2019 Staff Assessment of Flooding Focused Evaluation L-19-189, 54010-CALC-01, Davis-Besse Nuclear Power Station: Evaluation of Risk Significance of Permanent ILRT Extension.2019-07-29029 July 2019 54010-CALC-01, Davis-Besse Nuclear Power Station: Evaluation of Risk Significance of Permanent ILRT Extension. ML22262A1522019-05-0101 May 2019 Framatome Inc., Document ANP-2718NP, Revision 007, Appendix G Pressure-Temperature Limits for 52 EFPY for the Davis-Besse Nuclear Power Station ML22202A4332019-04-30030 April 2019 Enclosure C: Framatome ANP-2718NP, Rev. 7, Appendix G Pressure-Temperature Limits for 52 EFPY for the Davis-Besse Nuclear Power Station L-18-108, Request to Extend Enforcement Discretion Provided in Enforcement Guidance Memorandum 15-002 for Tornado-Generated Missile Protection Non-Conformance Identified in Response to Regulatory Issue Summary 2015-06, Tornado Missile....2018-04-12012 April 2018 Request to Extend Enforcement Discretion Provided in Enforcement Guidance Memorandum 15-002 for Tornado-Generated Missile Protection Non-Conformance Identified in Response to Regulatory Issue Summary 2015-06, Tornado Missile.... ML18149A2812018-02-16016 February 2018 2017 ATI Environmental Inc. Midwest Laboratory Radiological Environmental Monitoring Program L-17-270, Notification of Emergency Core Cooling System (ECCS) Evaluation Model Change Pursuant to 10 CFR 50.462017-09-0101 September 2017 Notification of Emergency Core Cooling System (ECCS) Evaluation Model Change Pursuant to 10 CFR 50.46 ML17086A0322017-03-31031 March 2017 Enclosure B to L-17-105, Areva Report ANP-3542NP, Revision 1, Time-Limited Aging Analysis (TLAA) Regarding Reactor Vessel Internals Loss of Ductility at 60 Years L-17-088, Independent Spent Fuel Storage Installation Changes, Tests and Experiments2017-03-27027 March 2017 Independent Spent Fuel Storage Installation Changes, Tests and Experiments ML17026A0082016-12-31031 December 2016 Areva Report ANP-3542NP, Time-Limited Aging Analysis (TLAA) Regarding Reactor Vessel Internals Loss of Ductility for Davis-Besse Nuclear Power Station, Unit No. 1 at 60 Years (Non Proprietary) L-16-229, Submittal of Pressure and Temperature Limits Report, Revision 32016-07-28028 July 2016 Submittal of Pressure and Temperature Limits Report, Revision 3 L-16-148, Fatigue Monitoring Program Evaluation of Reactor Coolant Pressure Boundary Components for Effects of the Reactor Coolant Environment on Fatigue Usage (I.E., Environmentally-Assisted Fatigue)2016-04-21021 April 2016 Fatigue Monitoring Program Evaluation of Reactor Coolant Pressure Boundary Components for Effects of the Reactor Coolant Environment on Fatigue Usage (I.E., Environmentally-Assisted Fatigue) L-15-288, Response to NRC Letter. Request for Information, Per 10 CFR 50.54(f) Regarding Recommendations 2.1. 2.3. and 9.3. of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2015-10-0202 October 2015 Response to NRC Letter. Request for Information, Per 10 CFR 50.54(f) Regarding Recommendations 2.1. 2.3. and 9.3. of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident ML15230A2892015-08-25025 August 2015 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50 Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Review L-14-401, First Energy Nuclear Operating Company (FENOC) Expedited Seismic Evaluation Process (ESEP) Reports Response to NRC Request for Information Pursuant to 10 CFR50.54(f) Regarding Recommendation.1 of the Near-Term Task Force (NTTF) Review of In2014-12-19019 December 2014 First Energy Nuclear Operating Company (FENOC) Expedited Seismic Evaluation Process (ESEP) Reports Response to NRC Request for Information Pursuant to 10 CFR50.54(f) Regarding Recommendation.1 of the Near-Term Task Force (NTTF) Review of In ML14353A0602014-11-0303 November 2014 2734296-R-010, Rev. 0, Expedited Seismic Evaluation Process (ESEP) Report Davis-Besse Nuclear Power Station L-14-289, Pressure and Temperature Limits Report. Revision 22014-09-22022 September 2014 Pressure and Temperature Limits Report. Revision 2 L-14-259, Firstenergy Nuclear Operating Company'S (Fenoc'S) Third Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)2014-08-28028 August 2014 Firstenergy Nuclear Operating Company'S (Fenoc'S) Third Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) ML14141A5252014-06-30030 June 2014 Staff Assessment of the Flooding Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima DAI-ICHI Nuclear Power Plant Accident L-14-167, Report of Facility Changes, Tests and Experiments for the Period Ending May 26, 20142014-06-18018 June 2014 Report of Facility Changes, Tests and Experiments for the Period Ending May 26, 2014 ML14134A5172014-05-30030 May 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima DAI-ICHI Nuclear Power Plant Accident L-14-148, CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2014-05-19019 May 2014 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models ML14112A3152014-04-21021 April 2014 Review of Draft Plant-Specific Supplement 52 to the Generic Environmental Impact Statement for License Renewal of Nuclear Plants Regarding L-14-104, Firstenergy Nuclear Operating Co. Response to NRC Request for Information Pursuant to 10 CFR 50.54 (F) Regarding the Flooding Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2014-03-11011 March 2014 Firstenergy Nuclear Operating Co. Response to NRC Request for Information Pursuant to 10 CFR 50.54 (F) Regarding the Flooding Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident ML14007A6702014-02-21021 February 2014 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) ML14042A2942014-02-19019 February 2014 Mega-Tech Services, LLC, Technical Evaluation Report Regarding the Overall Integrated Plan for Davis-Besse Nuclear Power Station, TAC No.: MF0961 ML13340A1592013-11-26026 November 2013 Davis-Besse Nuclear Power Station Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report Revision 1, Appendix a ML13340A1472013-11-26026 November 2013 Davis-Besse Nuclear Power Station & Perry Nuclear Power Plant - Response to RAI Associated with Seismic Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident (TAC Nos. MF0116 & MF0 ML13340A1632013-10-0909 October 2013 Davis-Besse Nuclear Power Station Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report Revision 1, Appendix C to Appendix G ML13340A1622013-10-0909 October 2013 Davis-Besse Nuclear Power Station Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report Revision 1, Appendix B (2 of 2) ML13340A1602013-10-0909 October 2013 Davis-Besse Nuclear Power Station Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report Revision 1, Appendix B (1 of 2) ML13340A1582013-10-0909 October 2013 Davis-Besse Nuclear Power Station Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report Revision 1 L-13-154, CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2013-05-28028 May 2013 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models L-13-157, Generic Safety Issue 191 Resolution Plan2013-05-15015 May 2013 Generic Safety Issue 191 Resolution Plan ML13009A3752012-12-12012 December 2012 Enclosure B to L-12-444, Calculation No. 32-9195651-000, Equivalent Margins Assessment of Davis-Besse Transition Welds for 52 EFPY - Non-Proprietary. L-12-347, FENOC Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Flooding Aspects of Recommendation 2.3 of Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident2012-11-27027 November 2012 FENOC Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Flooding Aspects of Recommendation 2.3 of Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident ML13135A2442012-08-10010 August 2012 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix B - Seismic Walkdown Checklists (Swcs), Sheet 1 of 379 Through Sheet 201 of 379 ML13135A2432012-08-10010 August 2012 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix a - Resumes and Qualifications ML13135A2422012-08-10010 August 2012 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Cover Through Page 176 2024-06-05
[Table view] Category:Technical
MONTHYEARL-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-22-253, Submittal of Pressure and Temperature Limits Report, Revision 52023-01-10010 January 2023 Submittal of Pressure and Temperature Limits Report, Revision 5 L-22-211, Technical Specification 5.6.6 Steam Generator Tube Inspection 180-Day Report2022-09-29029 September 2022 Technical Specification 5.6.6 Steam Generator Tube Inspection 180-Day Report L-22-216, Submittal of Pressure and Temperature Limits Report. Revision 42022-09-27027 September 2022 Submittal of Pressure and Temperature Limits Report. Revision 4 L-22-149, Post Accident Monitoring Report2022-06-23023 June 2022 Post Accident Monitoring Report ML22202A4362022-04-0808 April 2022 Enclosure F: Updated Inputs to 52 EFPY P-T Operating Curves ML22202A4372022-03-0202 March 2022 Enclosure G: Framatome Inc. Document 86-9344713-000, Davis-Besse Reactor Vessel Embrittlement Fluence Reconciliation Through 60 Years ML21322A2892021-12-0909 December 2021 Approval of Plant-Specific Analysis of Certain Reactor Vessel Internal Components in Accordance with License Renewal Commitment No. 53 ML20302A3022020-09-25025 September 2020 1 to Technical Requirements Manual ML19255H0992019-10-10010 October 2019 Staff Assessment of Flooding Focused Evaluation L-19-189, 54010-CALC-01, Davis-Besse Nuclear Power Station: Evaluation of Risk Significance of Permanent ILRT Extension.2019-07-29029 July 2019 54010-CALC-01, Davis-Besse Nuclear Power Station: Evaluation of Risk Significance of Permanent ILRT Extension. ML22262A1522019-05-0101 May 2019 Framatome Inc., Document ANP-2718NP, Revision 007, Appendix G Pressure-Temperature Limits for 52 EFPY for the Davis-Besse Nuclear Power Station ML22202A4332019-04-30030 April 2019 Enclosure C: Framatome ANP-2718NP, Rev. 7, Appendix G Pressure-Temperature Limits for 52 EFPY for the Davis-Besse Nuclear Power Station ML18149A2812018-02-16016 February 2018 2017 ATI Environmental Inc. Midwest Laboratory Radiological Environmental Monitoring Program L-17-270, Notification of Emergency Core Cooling System (ECCS) Evaluation Model Change Pursuant to 10 CFR 50.462017-09-0101 September 2017 Notification of Emergency Core Cooling System (ECCS) Evaluation Model Change Pursuant to 10 CFR 50.46 ML17086A0322017-03-31031 March 2017 Enclosure B to L-17-105, Areva Report ANP-3542NP, Revision 1, Time-Limited Aging Analysis (TLAA) Regarding Reactor Vessel Internals Loss of Ductility at 60 Years ML17026A0082016-12-31031 December 2016 Areva Report ANP-3542NP, Time-Limited Aging Analysis (TLAA) Regarding Reactor Vessel Internals Loss of Ductility for Davis-Besse Nuclear Power Station, Unit No. 1 at 60 Years (Non Proprietary) L-16-229, Submittal of Pressure and Temperature Limits Report, Revision 32016-07-28028 July 2016 Submittal of Pressure and Temperature Limits Report, Revision 3 L-15-288, Response to NRC Letter. Request for Information, Per 10 CFR 50.54(f) Regarding Recommendations 2.1. 2.3. and 9.3. of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2015-10-0202 October 2015 Response to NRC Letter. Request for Information, Per 10 CFR 50.54(f) Regarding Recommendations 2.1. 2.3. and 9.3. of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident L-14-289, Pressure and Temperature Limits Report. Revision 22014-09-22022 September 2014 Pressure and Temperature Limits Report. Revision 2 ML14134A5172014-05-30030 May 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima DAI-ICHI Nuclear Power Plant Accident L-14-148, CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2014-05-19019 May 2014 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models ML14112A3152014-04-21021 April 2014 Review of Draft Plant-Specific Supplement 52 to the Generic Environmental Impact Statement for License Renewal of Nuclear Plants Regarding ML14007A6702014-02-21021 February 2014 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) ML14042A2942014-02-19019 February 2014 Mega-Tech Services, LLC, Technical Evaluation Report Regarding the Overall Integrated Plan for Davis-Besse Nuclear Power Station, TAC No.: MF0961 L-13-154, CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2013-05-28028 May 2013 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models ML13009A3752012-12-12012 December 2012 Enclosure B to L-12-444, Calculation No. 32-9195651-000, Equivalent Margins Assessment of Davis-Besse Transition Welds for 52 EFPY - Non-Proprietary. ML13008A0612012-08-10010 August 2012 Davis-Besse Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix C, Area Walk-By Checklists, Sheet 21 of 139 Through End L-15-328, Enclosure 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. Part 7 of 72012-07-30030 July 2012 Enclosure 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. Part 7 of 7 ML15299A1502012-07-30030 July 2012 Enclosure 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. Part 6 of 7 ML15299A1492012-07-30030 July 2012 Enclosure 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. Part 5 of 7 ML15299A1482012-07-30030 July 2012 Enclosure 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. Part 4 of 7 ML15299A1472012-07-30030 July 2012 Enclosure 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. Part 3 of 7 ML15299A1462012-07-30030 July 2012 Enclosure 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. Part 2 of 7 ML15299A1442012-07-30030 July 2012 Enclosure 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. Part 1 of 7 ML12209A2602012-07-26026 July 2012 Attachment 31, Fauske & Associates, Inc. Technical Bulletin No. 1295-1, BWR MSIV Leakage Assessment: NUREG-1465 Vs. MAAP 4.0.2 ML1017400422010-06-0404 June 2010 0800368.407, Rev. 0, Summary of Design and Analysis of Weld Overlays for Reactor Coolant Pump Suction and Discharge, Cold Leg Drain, and Core Flood Nozzle Dissimilar Metal Welds for Alloy 600 Primary Water Stress Corrosion Cracking Mitigati L-10-132, 0800368.408, Revision 0, Summary of Weld Overlay Ultrasonic Examinations for Reactor Coolant Pump Suction and Discharge Nozzle Welds, Core Flood Nozzle Welds, and Cold Leg Drain Nozzle Welds2010-04-25025 April 2010 0800368.408, Revision 0, Summary of Weld Overlay Ultrasonic Examinations for Reactor Coolant Pump Suction and Discharge Nozzle Welds, Core Flood Nozzle Welds, and Cold Leg Drain Nozzle Welds ML1002501322010-01-11011 January 2010 0800368.404, Revision 1, Leak-Before-Break Evaluation of Reactor Coolant Pump Suction and Discharge Nozzle Weld Overlays for Davis-Besse Nuclear Power Station, Enclosure B ML11301A2222008-12-0101 December 2008 Reference: Combined Heat and Power Effective Energy Solutions for a Sustainable Future ML0821900132008-08-0707 August 2008 Monthly Operating Reports Second Quarter 2008 L-08-105, Reactor Head Inspection Report2008-04-11011 April 2008 Reactor Head Inspection Report L-08-005, Submittal of the 2007 Organizational Safety Culture and Safety Conscious Work Environment Independent Assessment Report for Davis-Besse2008-01-27027 January 2008 Submittal of the 2007 Organizational Safety Culture and Safety Conscious Work Environment Independent Assessment Report for Davis-Besse ML0726105652007-09-17017 September 2007 Confirmatory Order, 2007 Independent Assessment of Corrective Action Program (FENOC) ML0708602822007-03-15015 March 2007 Review and Analysis of the Davis-Besse March 2002 Reactor Pressure Vessel Head Wastage Event, Appendix B, Crack Driving Force and Growth Rate Estimates ML0708602812007-03-15015 March 2007 Review and Analysis of the Davis-Besse March 2002 Reactor Pressure Vessel Head Wastage Event, Appendix a, Finite Element Stress Analysis of Davis-Besse CRDM Nozzle 3 Penetration ML0708602802007-03-15015 March 2007 Review and Analysis of the Davis-Besse March 2002 Reactor Pressure Vessel Head Wastage Event, Section 10. the Unique Nature of the Davis-Besse Nozzle 3 Crack and the RPV Head Wastage Cavity ML0708602762007-03-15015 March 2007 Review and Analysis of the Davis-Besse March 2002 Reactor Pressure Vessel Head Wastage Event, Section 9. Cfd Modeling of Fluid Flow in CRDM Nozzle and Weld Cracks and Through Annulus ML0708602712007-03-15015 March 2007 Review and Analysis of the Davis-Besse March 2002 Reactor Pressure Vessel Head Wastage Event, Section 8. Stress Analysis and Crack Growth Rates for Davis-Besse CRDM Nozzles 2 and 3 ML0708602842007-03-15015 March 2007 Review and Analysis of the Davis-Besse March 2002 Reactor Pressure Vessel Head Wastage Event, Appendix C, Cfd Analysis 2024-06-05
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FENOCc 5501 North State Route 2FirstEnergy Nuclear Operating CompanyRaymond A. Lieb 419-321-7676Vice President, Nuclear Fax: 419-321-7582April 21, 2014L-14-146 10 CFR 54ATTN: Document Control DeskU.S. Nuclear Regulatory CommissionWashington, DC 20555-0001SUBJECT:Davis-Besse Nuclear Power Station, Unit No. 1Docket No. 50-346, License Number NPF-3Review of Draft Plant-Specific Supplement 52 to the Generic Environmental ImpactStatement for License Renewal of Nuclear Plants Regarding Davis-Besse NuclearPower Station, Unit 1 (TAC No. ME4613)By letter dated August 27, 2010 (Agencywide Documents Access and ManagementSystem (ADAMS) Accession No. ML1 02450565), FirstEnergy Nuclear OperatingCompany (FENOC) submitted an application pursuant to Title 10 of the Code of FederalRegulations, Part 54 for renewal of Operating License NPF-3 for the Davis-BesseNuclear Power Station, Unit No. 1 (Davis-Besse). By letter dated February 24, 2014(ML14050A078 (LTR), ML14050A523 (PKG), ML14050A521 (FRN)), the NuclearRegulatory Commission (NRC) issued the Notice of Availability of Draft Plant-SpecificSupplement 52 to the Generic Environmental Impact Statement for License Renewal ofNuclear Plants Regarding Davis-Besse Nuclear Power Station, Unit 1.FENOC has completed its review of Draft Plant-Specific Supplement 52 to the GenericEnvironmental Impact Statement for License Renewal of Nuclear Plants RegardingDavis-Besse Nuclear Power Station, Unit 1. The Enclosure provides FENOC commentson the document.There are no regulatory commitments contained in this letter. If there are any questionsor if additional information is required, please contact Mr. Clifford I. Custer, FleetLicense Renewal Project Manager, at 724-682-7139.Sincerej,aym nd A. Liegb Davis-Besse Nuclear Power Station, Unit No. 1L-14-146Page 2Enclosure:FirstEnergy Nuclear Operating Company (FENOC) Comments Related to DraftPlant-Specific Supplement 52 to the Generic Environmental Impact Statement forLicense Renewal of Nuclear Plants Regarding Davis-Besse Nuclear PowerStation, Unit 1 (DSEIS)cc: Ms. Cindy Bladey, Chief, Rules, Announcements, and Directives BranchNRC DLR Environmental Project ManagerNRC DLR Project ManagerNRC Region III Administratorcc: w/o EnclosureNRC DLR DirectorNRR DORL Project ManagerNRC Resident InspectorUtility Radiological Safety Board
Enclosure
Davis-Besse Nuclear Power Station, Unit No. I (Davis-Besse)Letter L-14-146FirstEnergy Nuclear Operating Company (FENOC) Comments Related toDraft Plant-Specific Supplement 52 to theGeneric Environmental Impact Statement for License Renewal of Nuclear PlantsRegarding Davis-Besse Nuclear Power Station, Unit 1 (DSEIS)14 pages follow FirstEnergy Nuclear Operating Company (FENOC) CommentsRelated to Draft Plant-Specific Supplement 52 to theGeneric Environmental Impact Statement for License Renewal of Nuclear PlantsRegarding Davis-Besse Nuclear Power Station, Unit 1 (DSEIS)L-14-146Page 1 of 14DSEISItem DSEIS Page / CommentNo. Section LnesLine(s)1. General -- Although the DSEIS discusses the revised GElS and theComment related final rule, FENOC believes that the discussionshould be further clarified to confirm that, as applicable toDavis-Besse, the NRC has considered each of theCategory 1 issues in the revised rule and determined thatthere is no new and significant information and theCategory 1 determinations remain valid for Davis-Besseand/or provided a justification for any differences betweenwhat is in the DSEIS versus what is in the revisedGElS/final rule.2. Abstract iii / FENOC notes that the description of the combinationsLines 9-10 alternative on this page does not match the similardescription on page xix, Line 7.3. Executive xv / FENOC suggests changing "Nuclear Power Plant" toSummary Line 5 "Nuclear Power Station".4. Executive xvi / FENOC recommends changing "is" to "are", since theSummary Line 30 topic is "environmental impacts".5. Executive xix The DSEIS concludes that its "preliminarySummary recommendation is that the adverse environmentalimpacts of license renewal for Davis-Besse are not great1.5 enough to deny the option of license renewal for energy-planning decisionmakers." Consistent with 10 CFR§ 51.95(c)(4) and Section 9.4 of the DSEIS, thisconclusion should be revised to read as follows: "theadverse environmental impacts of license renewal arenot so great that preserving the option of licenserenewal for energy planning decision makers wouldbe unreasonable."6. Abbreviations xxii FENOC suggests that the word "million" following MMBtu& Acronyms should be in the right-hand column in front of "Britishthermal unit".
FENOC Comments Related to Draft DSEISL-14-146Page 2 of 14DSEISItem DSEIS SINo. Section Page / CommentLine(s)7. 1.4 1-4 / This background sentence on the 2013 rulemaking statesLines 10-13 that the new Category 1 issues set forth in the revisedGElS and Part 51 rules "include geology and soils,Appendix B B-1 / exposure of terrestrial organisms to radionuclides,last exposure of aquatic organisms to radionuclides, humanparagraph health impact from chemicals, and physical occupationalhazards." A similar statement appears in Appendix B.This list does not appear to be comprehensive. The finalrule (78 Fed. Reg. at 37,283) states: "New Category 1issues were added: geology and soils; effects of dredgingon surface water quality; groundwater use and quality;exposure of terrestrial organisms to radionuclides;exposure of aquatic organisms to radionuclides; effects ofdredging on aquatic organisms; impacts of transmissionline right-of-way management on aquatic resources;employment and income; tax revenues; human healthimpacts from chemicals; and physical occupationalhazards." and "Several issues were changed fromCategory 2 to Category 1: Offsite land use, air quality,public services (several issues), and population andhousing."FENOC requests that the DSEIS be revised to add all ofthe new Category 1 issues to this background sentence orto specifically clarify that this sentence is not intended tobe comprehensive or to match the scope of new issuesevaluated in the DSEIS.Relatedly, and as proposed below regarding thesubstantive evaluations in Chapters 3 and 4, FENOCwants to ensure that all new Category 1 issues are fullyand clearly addressed, or a justification be included forthose not otherwise addressed in the DSEIS.
FENOC Comments Related to Draft DSEISL-1 4-146Page 3 of 14Item DSEIS DSEISNo. Section Page / CommentLine(s)8. 1.4 1-4 / This background sentence on the 2013 rulemaking statesLines 13-15 that "Radionuclides released to groundwater, effects onterrestrial resources (non-cooling system impacts),Appendix B B-1 / minority and low-income populations (i.e., environmentallast justice), and cumulative impacts were added as newparagraph Category 2 issues."This list appears to be inconsistent with the final rule (78Fed. Reg. at 37,283), which states: "New Category 2issues were added: Radionuclides released togroundwater, water use conflicts with terrestrialresources, water use conflicts with aquatic resources, andcumulative impacts." and "One uncharacterized issue wasreclassified as Category 2: Environmental justice/minorityand low-income populations."FENOC requests that the DSEIS be revised to include allof the new Category 2 issues to this background sentenceor to specifically clarify that this sentence is not intendedto be comprehensive.9. 1.4 1-4/ This paragraph discusses the effectiveness of the finalLines 16-22 rule with regard to the new or revised Category 1 and 2issues, and explains that the NRC must consider them.FENOC recommends that the NRC add a brief discussionproviding additional details, explaining how the NRCconsidered the Category 1 and 2 issues.10. 1.5 1-6 / Similar to Comment 5, above, the sentence should beLines 6-7 revised to read as follows: "... Commission that theadverse environmental impacts of license renewal arenot so great that preserving the option of licenserenewal for energy planning decision makers wouldbe unreasonable."11. 1.10 1-9/ FENOC suggests changing "Accession Nos." to theLine 5 singular "Accession No.".12.2.02-1 /Lines 2 & 5FENOC suggests removing the extra spaces (25 mi) (40km) (2500 m) in lines 2 & 5. Also, the statement"[a]pproximately 700 ac (300 ha) are marshland..." is theonly location in the DSEIS where 700 ac is used;elsewhere, the statement "approximately 733 ac" is usedmultiple times. Recommend using "approximately 733 ac"throughout the DSEIS.
FENOC Comments Related to Draft DSEISL-1 4-146Page 4 of 14DSEISItem DSEIS PaeICNo. Section Page / CommentLine(s)13. 2.1 2-1 / FENOC recommends the use of 908 megawatts-electricLine 19, (MWe) instead of 913 MWe in the DSEIS, to be consistentwith the License Renewal Application and Environmental2.1.1 2-6 / Report. The reference cited on page 2-6, Line 11 (i.e.,Line 9 FENOC 201 Oc), is the License Renewal Application,which lists electrical output as "908 MWe". Also, 908 MWeis used later in the DSEIS for the comparison ofAlternatives.14. 2.1.1 2-6 / The sentence states that each primary coolant loopLine 17 contains one reactor coolant pump, but Davis-Besse hastwo reactor coolant pumps per loop. FENOC recommendschanging Line 17 from "... one reactor coolant pump," to"... one or two (depending on the plant design)reactor coolant pumps,".15. 2.1.2.3 2-10 / FENOC suggests revising the 3 cited references (FENOCLines 12, 17 2011) on this page to be consistent with the references& 27 Section 2.4, which lists the references as FENOC 2011 a,2011b, or 2011c.2-11/ Same comment for page 2-11, line 26 (FENOC 2010),Line 26 which has no alpha character (a, b, c or d) following theyear.16. 2.2.1 2-18/ The Magee Marsh Wildlife Area entrance is approximatelyLine 19 6 miles west of the station. Lake Erie is east of the station.FENOC recommends revising Line 19 to read, "TheNavarre Marsh partially surrounds the station to the north,east and southeast."17. 2.2.2.1 2-21 / Regarding the sentence, "Davis-Besse has many sourcesLine 15 of criteria pollutants and HAPs to include the followincq:",FENOC recommends changing the sentence to read:"The Davis-Besse sources of criteria pollutants andHAPS are as follows:" As currently written, the sentencesuggests there are more sources than those listed.18. 2.2.2.1 2-21 / FENOC requests that, at the beginning of the sentence atLine 44 the end of the Line, NRC consider adding "However," infront of "In 1992, Davis-Besse..." to make it clear that theprevious discussion of fires and the chemicals releasedduring transformer fires didn't apply in this case.19. 2.2.4 2-27 / FENOC recommends changing "Augqust 14, 2006" toLine 12 "July 1. 2011" to align with the new permit date and thesuggested update to Appendix C, below.
FENOC Comments Related to Draft DSEISL-14-146Page 5 of 14Item DSEIS DSEISNo. Section Page I CommentLine(s)20. 2.2.4 2-28 / FENOC recommends deleting "asbestos", because theLine 23 updated permit does not require monitoring for asbestos.21. 2.2.4 2-28 / FENOC recommends changing or deleting the referenceLine 25 source cited (Brown 2010) since there is nocorresponding reference citation in the references list inSection 2.4.22. 2.2.4 2-29 / FENOC recommends changing "2006" to "2011" to alignLine 7 with the new permit date, a previous comment and thesuggested update to Appendix C, below.23. 2.2.4 2-29 / The use of the terms "violate" with respect to NPDESLines 16-18 requirements and "NOV" (Notice of Violation issued by aregulator e.g., OEPA) are confusing when usedinterchangeably in the first two sentences. Thestatements need to be clear that site personnel mayindicate an action, lack of action, or parameter may haveexceeded ("violated") permit requirements, but there wereno formal NOVs issued for the cases described whereFENOC exceeded permit requirements for a period oftime. FENOC recommends changing "NOV" on line 17 to"violations".24. 2.2.4 2-29 / The change has been submitted and approved, and zincLines 26-27 acetate is being used, so FENOC recommends revisingthe last sentence to be past tense.25. 2.2.5 2-31 / FENOC recommends changing the sentence to read,Line 4 "...December 2010 at monitoring wells 30S...".26. 2.2.5 2-33 / FENOC recommends changing "Ce-1 37" to "Cs-1 37" andLines 13-14 "Ce-i134" to "Cs-134".Also, the cited reference (NRC 1991) is not included inthe list of references in Section 2.4, page 2-87.27. 2.2.5 2-33 / FENOC recommends changing "sodium hydroxide" toLine 30 "sodium hypochlorite".28. 2.2.8.3 2-49 / FENOC suggests that the reference to "Table 2.3-8" inLine 13 this line should instead be "Table 2.2-8."29. 2.2.8.4 2-52 / FENOC suggests that the reference to "Section 2.2.6" inLine 6 this line should instead be "Section 2.2.7.2."30. 2.2.9.2 2-59 / FENOC suggests underlining and separating the headingLine 10 "Transportation" in a manner similar to the formatting ofthe previous heading "Education".
FENOC Comments Related to Draft DSEISL-1 4-146Page 6 of 14Item DSEIS DSEISNo. Section Page / CommentLine(s)31. 2.2.9.5 2-60 / A space is needed between the first two words in the line.Line 4232. 2.2.9.5 2-65 / The word "temporary" is missing the letter "t".Line 1133. 2.2.9.6 2-67 / There is an errant comma following the word "of'.Line 1234. 2.2.10.1 2-69 / FENOC recommends rewording the following sentence asLines 21-22 shown: "One documented fluted projectile point is6leeatedwas discovered at the Peters site in Ottawa County,south of Davis-Besse along the Portage River wasdie6eered (Prufer and Shane 1973)."35. 2.2.10.1 2-71 / FENOC recommends changing "north" to "northwest",Line 23 because the Maumee River runs from the southwest tothe northwest of Davis-Besse.36. 2.2.10.2 2-72 / The Magee Marsh is approximately 6 miles west of Davis-Line 40 Besse. FENOC recommends adding a period after"...agricultural purposes" and deleting the remainder ofthe sentence.37. 2.4 2-74 Many of the titles for the Code of Federal Regulationsto 2-76 / citations are incorrect or duplicated. Examples includel0various CFR Part 60, Part 70, 15 CFR Part 930 has multipleLines citations bundled together, 40 CFR Part 80, 40 CFR Part239, etc. FENOC recommends verifying the titles forthese citations in this section and in the other referencessections of the DSEIS.38. 2.4 2-79 FENOC suggests that the title of this document referenceLine 24 should read, "Loggerhead Shrike: First Ever Captured...".39. 2.4 2-82 FENOC recommends deleting the "(2010b)" at the end ofLine 37 the reference to be consistent with the other FENOC 2010citations.40. 2.4 2-83 / This FENOC 2011 citation appears to be out ofLines 15-19 chronological order and should be located between linesand Line 20 11 and 12.On line 20, [FENCOl should read [FENOC].
FENOC Comments Related to Draft DSEISL-1 4-146Page 7 of 14Item DSEIS DSEISNo. Section Page / CommentLine(s)41. Chapters All Although these substantive chapters evaluating the3 & 4 environmental impacts of refurbishment and operationappear to address most of the new issues in the June 20,2013 final rule that revised Table B-i, it is not clearwhether each individual issue has been addressed.For example, it does not appear to be clearly statedwhether the following Category 1 issues are applicable toDavis-Besse and, if so, how they are addressed: effectsof dredging on surface water quality, groundwater qualitydegradation resulting from water withdrawals, effects ofdredging on aquatic organisms, and impacts oftransmission line ROW management on aquaticresources.Therefore, FENOC recommends that the NRC include adiscussion in this chapter, or elsewhere in the SEIS, toprovide an explanation of how the Category 1 issues inthe new final rule have been addressed, or, in thealternative, to provide a justification for any differencesbetween what is in the DSEIS versus what is in therevised GElS/final rule.42. 3.1 3-3 / There are numerous references in Chapters 3 & 4 toLines 5 & 6 replacement of the steam generators and that theseactivities "will be performed during an extended outagescheduled for the spring of 2014" (e.g., Pg 3-3, lines 17-20). At the time of this review, both steam generatorshave been replaced and the 2014 refueling outage isnearing completion. Consider changing the tense forsteam generator replacement to past tense, althoughFENOC realizes that this change would impact manypages and sections of the DSEIS.43. 3.2.1 3-4 / FENOC is an entity. FENOC recommends changing theLine 33 sentence from "FENOC noted in their ER that..." to"FENOC noted in its ER that...". This issue appears inmultiple locations (at least 8 instances) in the DSEIS (seeChapter 4 for more examples).3-5 / Similarly, FENOC recommends changing the statement inLine 1 Line 1 on the next page from "FENOC's proceduresrequire them to coordinate with the FWS..." to "FENOC'sprocedures require coordination with the FWS..."44. 3.2.8 3-9 / FENOC recommends changing "EnvironmentalLine 7 Procedure" to "Environmental Evaluations procedure" tomatch the title of the procedure.
FENOC Comments Related to Draft DSEISL-1 4-146Page 8 of 14Item DSEIS DSEISNo. Section Page I CommentLine(s)45. 4.7.3 4-8 / FENOC recommends deleting one of the uses of the word[No line "vicinity" in the 2nd paragraph, 1st sentence.numbers]46. 4.9.1 4-13 / The first sentence begins with an errant period.[No linenumbers]47. 4.14 4-30 & FENOC requests that the DSEIS be revised to include an4-31 affirmative statement in this section clarifying that theNRC has reviewed the Category 1 issues in Table B-i, asrevised in the June 20, 2013 final rule, and hasdetermined that, to the extent such topics are applicableto Davis-Besse, there is no new and significantinformation, and therefore the Category 1 designations forthese issues remain correct and the small impactdesignations in Table B-1 remain correct. Alternatively,the SEIS should provide a justification for any differencesbetween what is in the DSEIS versus what is in therevised GElS/final rule.48. Table 4-32 & 4-33 At the bottom of page 4-32, the first project listed under4.15-1 "Energy Projects" is the 'Independent Spent Fuel StorageInstallation on Davis-Besse site; dry spent-fuel storage'. Itis not clear why the Status discusses Spent Fuel Pool andtransfer pit storage versus the dry fuel storage pad andcurrent dry fuel storage capability.On page 4-33, the 3rd PROJECT/ACTION listed (ToledoRefinery Substation Project), the LOCATION descriptionends abruptly... "Oregon, Ohio, near the intersection of'.49. 4.15.5.2 4-43 / The sentence at the end of the second paragraph in thisLine 20 section is not complete and has no period.
FENOC Comments Related to Draft DSEISL-1 4-146Page 9 of 14Item DSEIS DSEISNo. Section Page / CommentLine(s)50. 5.3.1 5-3 / In response to NRC requests for additional informationLines (RAIs), the total number of SAMAs was changed from 16723 & 33 to 168, and the number of SAMAs eliminated based onscreening was changed from 152 to 153. (see ADAMS5.3.3 5-6 / Accession No. ML1 11 80A233 [FENOC Letter L-1 1-154Lines 12, 21 dated June 24, 2011], RAI 5.c).This comment also applies to Appendix F, Section F.1F. 1 F-1 / (page F-1). However, since this Appendix is writtenLine 18 chronologically, FENOC recommends adding thefollowing bullet to page F-2 under the list of FENOCF-2 / provided information via letter dated June 24, 2011:Lines 4-23 -identification of a new SAMA candidate (OT-9R),which changed the total number of SAMA candidatesevaluated to 168 instead of the original 167.51. 5.3.1 5-3 / FENOC suggests adding the text in bold/underline: "In theLines 35-36 third step, FENOC estimated the benefits and the costsassociated with each of the 15 candidate SAMAs."52. 5.3.2 5-4 / The text states: "Column totals in Table 5.3-2 may differLine 29 due to round off." The table reference appears to beincorrect. The correct reference is Table 5.3-1.53. 5.3.2 5-5 / FENOC recommends clarifying the following two initiatingTable 5.3-1 event descriptions:From:"Flooding in CCW pump room"F.2.1 F-4 /Table F-1 To:"Flooding in CCW pump room from SW" [or, ServiceWater]and, From:"Flooding in turbine building"To:"Flooding in turbine building from Circ water"Also, consider noting that the % contribution to CDFvalues are slightly different from those reported in FENOCEnvironmental Report Table E.3-1 due to rounding.Comment also applies to Appendix F, Section F.2.1,Table F-I.
FENOC Comments Related to Draft DSEISL-1 4-146Page 10 of 14Item DSEIS DSEISNo. Section Page / CommentLine(s)54. 5.3.2 5-5 / FENOC recommends that the Population Dose andTable 5.3-2 % Contribution be updated to match those included inFENOC Letter L-12-244 dated July 16, 2012 (see TableF.2.1 F-5I E.3-21).Table F-2 Comment also applies to Appendix F, Section F.2.1,Table F-2.55. 5.3.5 5-7 / Suggest adding the text in bold/underline: "FENOC'sLines 13-14 derivation of each of the associated costs is summarizedin Appendix E of the ER."56. 6.2.1.2 6-5 / The DSEIS states that the various studies it reviewedLines 19-21 show that "the relatively lower order of magnitude of GHGemissions from nuclear power, when compared to fossil-fueled alternatives (especially natural gas), couldpotentially disappear if available uranium ore grades dropsufficiently.. ." (Emphasis added.) This statement isspeculative, apparently based on worst-caseassumptions, and a review of the data presented in Table6.2-2 reveals it to be unsupported. See, e.g., POST(2006) (referenced and described in Table 6.2-2). FENOCrecommends deleting this sentence.57. 6.2.2 6-8 / The DSEIS states that "[flew studies predict that nuclearLines 39-40 fuel cycle emissions will exceed those of fossil fuels withina timeframe that includes the Davis-Besse period ofextended operation." But none of the studies cited inTable 6.2-2 appear to support this thesis-at least basedon the data presented. Therefore, FENOC suggestsrevising this sentence to state: "Nearly all studiespredict that nuclear fuel cycle emissions will remainan order of magnitude or more below those of alltypes of fossil fuels during the Davis-Besse period ofextended operation."58. 6.2.2 6-9 / The DSEIS concludes that "it is likely that GHG emissionsLines 8-9 from renewable energy sources would be lower thanthose associated with Davis-Besse at some point duringthe period of extended operation." This conclusionappears to be unsupported by the data presented in Table6.2-3. FENOC suggests revising this sentence to statethat "most of the relevant studies show that it is likelythat GHG emissions associated with Davis-Besse willremain comparable to or below those from renewableenergy sources throughout the period of extendedoperation."
FENOC Comments Related to Draft DSEISL-14-146Page 11 of 14Item DSEIS OSEISNo. Section Page / CommentLine(s)59. 8.0 8-3 / FENOC recommends changing "... FENOC ServiceLine 30 Company's..." to "... FirstEnergy Service Company's...."60. 8.1 8-6 / The conclusion that the air quality impacts of new naturalTable 8.1-1 gas combined cycle generation would be SMALL toMODERATE appears inappropriate, in that it blurs thesignificant difference between emissions from Davis-Besse and natural gas sources. See Table 6.2-2 (page6-6). FENOC suggests that if the impacts from Davis-Besse are SMALL, then the impacts from natural gasfacilities should logically be at least MODERATE,consistent with the Davis-Besse Environmental Report.61. 8.1.5.1 8-12/ FENOC suggests revising the acronym "GGNS" to readLine 17 "Davis-Besse".62. 11.0 11-4 FENOC recommends changing the name "Nesser" toAppendix A A-4 & A-1 73 "Nusser" in 3 locations. Nusser is the correct spellingaccording to the signature on the email included as pageA-173.63. Appendix C C-5 / Storage of spent nuclear fuel & high-level radioactiveTable C-2 waste:STATUS -The word Expired should read "Expires".64. Appendix C C-5 / Permit to operate an air containment source:Table C-2 STATUS -should read as follows:Operation of station auxiliary boilerFacility ID#: 0362000091Permit#: P0110436Issued: 02/28/2013Expires: 02/28/202365. Appendix C C-5 & C-6 / NPDES Permit -Treatment of wastewater and effluentTable C-2 discharge to surface receiving waters (Toussaint Riverand Lake Erie):STATUS -the Ohio Permit No. should read21B0001 1*JDIssued: 07/01/2011Expires: 04/3012016 FENOC Comments Related to Draft DSEISL-14-146Page 12 of 14Item DSEIS DSEISNo. Section Page / CommentLine(s)66. Appendix C C-6 / Hazardous material registration:Table C-2 STATUS -should read as follows:Transportation of hazardous materialsPermit Number: 052112 020 004UWIssued: 05/22/2012Expires: 06/30/2015(Renewed Triennially)67. Appendix C C-6 / License to deliver radioactive waste:Table C-2 STATUS -should read as follows:Shipment of radioactive material to a licensed disposal-processing facility within the State of TennesseeTennessee Delivery License# T-0H003-L14Issued: AnnuallyExpires: 12/31/201468. Appendix C C-6 / New Row:Table C-2 License to deliver radioactive waste:AGENCY -should read as follows:South Carolina Department of Health andEnvironmental ControlAUTHORITY -should read as follows:South Carolina Radioactive Waste Transportation andDisposal Act No. 429 of 1980STATUS -should read as follows:Shipment of radioactive material to a licenseddisposal-processing facility within the State of SouthCarolinaPermit #: 0054-34-14Issued: 12/10/2013Expires: 12/31/2014 FENOC Comments Related to Draft DSEISL-14-146Page 13 of 14Item DSEIS DSEISNo. Section Page / CommentLine(s)69. Appendix C C-6 / Underground storage tank registration:Table C-2 STATUS -should read as follows:Gerifirate Facility # 62000072Expires: 06/30/201470. Appendix C C-7 / X-ray generating equipment registration:Table C-2 STATUS -should read as follows:Expires: 05/31/201471. Appendix C C-7 / Scientific Collection Permit:Table C-2 STATUS -should read as follows:Permit #: 15-112Issued: 03/16/2014Expires: 03/15/201572. Appendix E E-8 The following FENOC letter is missing from the list ofcorrespondence:Letter L-12-244 from John C. Dominy, Davis-BesseNuclear Power Station, Unit 1. Docket No. 50-346,License Number NPF-3, Correction of Errors in the Davis-Besse Nuclear Power Station. Unit No.1, LicenseRenewal Application (TAC No. ME4613) EnvironmentalReport Severe Accident Mitigation Alternatives Analysis,and License Renewal Application Amendment No. 29(dated July 16, 2012)FENOC notes that this same correspondence is listed inAppendix F, Section F.8 (References), page F-36, Lines34-38 (FENOC 2012a). However, the ML number listed inAppendix F is a duplicate of the ML number for FENOCletter dated June 24, 2011. Also, FENOC was not able tofind the document in ADAMS using various search terms(may not be available to the public).73. F.2.2 F-12 / FENOC suggests inserting the word "are" as follows: "TheLine 7 Level 1 core damage sequences are grouped into coredamage bins according to similarities in their impact oncontainment response."
FENOC Comments Related to Draft DSEISL-14-146Page 14 of 14DSEISItem DSEIS SINo. Section Page / CommentLine(s)74. F.2.2 F-14 / FENOC suggests editing the quoted sentence as follows:Lines 14-17 "Data from 2006 through 2008 was were considered, butthe 2006 data was were chosen because it-was theywere the most complete data set. Data from year 2008was-were considered unusable as it they contained toomany missing long data-sequences of unusable data."75. F.2.2 F-14 / FENOC suggests adding to the following sentence theLines 39-40 language in bold/underline: "In response to an NRC staffRAI, FENOC revised the Level 3 PRA to include thatportion of the Canadian population located within the50-mi radius SAMA analysis region (FENOC 2011)."76. F.3.1 F-17 / Same issue as Comment 49 [5.3.1]. Specifically, the totalLine 34 number of SAMAs was changed from 167 to 168, and thenumber of SAMAs eliminated based on screening wasF.7 F-35 / changed from 152 to 153.Lines However, since Appendix F is written chronologically,18 & 19 FENOC recommends adding the following sentence afterline 6 on page F-18 and after line 19 on page F-35:In response to NRC RAIs, FENOC's initial list of 167SAMA candidates was increased to 168, of which 153were eliminated based on screening.77. F.3.2 F-21 / FENOC suggests editing the quoted sentence as follows:Line 30 "In response to the RAIs, FENOC addressed thesuggested lower cost alternatives and determined thatthey were eitheF-already implemented at Davis-Besse (b),not feasible (c), or not cost-beneficial (a, d, e, and f)(FENOC 2011)."78. F.5 F-27 / The word "applicant's" should be "applicants'."Line 27