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Results
Other: AEP-NRC-2013-13, Redacted Version of Overall Integrated Plan in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis Events (Order Number EA-12-049), AEP-NRC-2013-14, Overall Integrated Plan in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051), AEP-NRC-2013-71, First Six Month Status Report in Response to March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies, AEP-NRC-2013-72, 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), AEP-NRC-2014-16, Six Month Status Report in Response to March 12, 2012, Commission Order Modifying Licensees with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051), AEP-NRC-2014-17, Second Six Month Status Report in Response to March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events..., AEP-NRC-2014-66, Third Six Month Status Report in Response to March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049), AEP-NRC-2014-67, 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), AEP-NRC-2014-89, Compliance with March 12, 2012, NRC Order Regarding Mitigation Strategies for Beyond-Design-Basis External Events, AEP-NRC-2014-91, Update to Communications Assessment Implementation Actions and Timeline - Fukushima Dai-ichi Near-Term Task Force Recommendation 9.3, Emergency Preparedness, AEP-NRC-2015-13, Fourth Six-Month Status Report in Response to March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049), AEP-NRC-2015-22, Compliance with March 12, 2012, NRC Order Regarding Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049), AEP-NRC-2015-23, Final Integrated Plan Regarding March 12, 2012, U.S. NRC Order Regarding Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049), AEP-NRC-2015-83, Revision 1 of Final Integrated Plan Regarding March 12, 2012, NRC Order Regarding Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049), ML13234A503, ML13357A325, ML14115A315, ML14140A064, ML14209A122, ML14216A362
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MONTHYEARAEP-NRC-2013-14, Overall Integrated Plan in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)2013-02-27027 February 2013 Overall Integrated Plan in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) Project stage: Other AEP-NRC-2013-13, Redacted Version of Overall Integrated Plan in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis Events (Order Number EA-12-049)2013-02-27027 February 2013 Redacted Version of Overall Integrated Plan in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis Events (Order Number EA-12-049) Project stage: Other ML13164A3812013-06-19019 June 2013 Request for Additional Information on the Overall Integrated Plan in Response to Order EA-12-051 Concerning Reliable Spent Fuel Pool Instrumentation Project stage: RAI ML13183A4312013-07-0303 July 2013 Online Reference Portal for Review of Mitigation Strategies Submittal in Response to Order EA-12-049 Project stage: Approval AEP-NRC-2013-57, Response to Request for Additional Information Regarding the Overall Integrated Plan in Response to Order EA-12-051, Issuance of Order to Modify Licenses with Regard to Reliable Spent Fuel Pool Instrumentation.2013-07-11011 July 2013 Response to Request for Additional Information Regarding the Overall Integrated Plan in Response to Order EA-12-051, Issuance of Order to Modify Licenses with Regard to Reliable Spent Fuel Pool Instrumentation. Project stage: Response to RAI AEP-NRC-2013-71, First Six Month Status Report in Response to March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies2013-08-26026 August 2013 First Six Month Status Report in Response to March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies Project stage: Other AEP-NRC-2013-72, 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)2013-08-26026 August 2013 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) Project stage: Other ML13234A5032013-08-28028 August 2013 Nuclear Regulatory Commission Audits of Licensee Responses to Mitigation Strategies Order EA-12-049 Project stage: Other ML13310B4992013-11-13013 November 2013 Interim Staff Evaluation and Request for Additional Information Regarding the Overall Integrated Plan for Instrumentation Project stage: RAI ML13357A3252014-01-10010 January 2014 Mega-Tech Services, LLC, Technical Evaluation Report Regarding the Overall Integrated Plan for Donald C. Cook Nuclear Plant, Units 1 and 2, TAC Nos.: MF0766 and MF0767 Project stage: Other ML13337A3252014-01-24024 January 2014 Interim Staff Evaluation and Audit Report Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) Project stage: Acceptance Review AEP-NRC-2014-16, Six Month Status Report in Response to March 12, 2012, Commission Order Modifying Licensees with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)2014-02-27027 February 2014 Six Month Status Report in Response to March 12, 2012, Commission Order Modifying Licensees with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) Project stage: Other AEP-NRC-2014-17, Second Six Month Status Report in Response to March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events...2014-02-27027 February 2014 Second Six Month Status Report in Response to March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events... Project stage: Other ML14115A3152014-04-28028 April 2014 Plan for the Onsite Audit of Mohr Regarding Implementation of Reliable Spent Fuel Pool Instrumentation Related to Order EA-12-051 Project stage: Other ML14140A0642014-05-21021 May 2014 Plan for the Onsite Audit Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Instrumentation Related to Orders EA-12-049 and EA-12-051 Project stage: Other ML14209A1222014-08-13013 August 2014 Report for the Audit Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 Project stage: Other AEP-NRC-2014-67, 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)2014-08-27027 August 2014 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) Project stage: Other AEP-NRC-2014-66, Third Six Month Status Report in Response to March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2014-08-27027 August 2014 Third Six Month Status Report in Response to March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) Project stage: Other ML14216A3622014-08-27027 August 2014 Report for the Onsite Audit of Mohr Regarding Implementation of Reliable Spent Fuel Pool Instrumentation Related to Order EA-12-051 Project stage: Other AEP-NRC-2014-91, Update to Communications Assessment Implementation Actions and Timeline - Fukushima Dai-ichi Near-Term Task Force Recommendation 9.3, Emergency Preparedness2014-12-16016 December 2014 Update to Communications Assessment Implementation Actions and Timeline - Fukushima Dai-ichi Near-Term Task Force Recommendation 9.3, Emergency Preparedness Project stage: Other AEP-NRC-2014-89, Compliance with March 12, 2012, NRC Order Regarding Mitigation Strategies for Beyond-Design-Basis External Events2014-12-16016 December 2014 Compliance with March 12, 2012, NRC Order Regarding Mitigation Strategies for Beyond-Design-Basis External Events Project stage: Other AEP-NRC-2015-13, Fourth Six-Month Status Report in Response to March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2015-02-25025 February 2015 Fourth Six-Month Status Report in Response to March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) Project stage: Other AEP-NRC-2015-23, Final Integrated Plan Regarding March 12, 2012, U.S. NRC Order Regarding Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2015-06-16016 June 2015 Final Integrated Plan Regarding March 12, 2012, U.S. NRC Order Regarding Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) Project stage: Other AEP-NRC-2015-22, Compliance with March 12, 2012, NRC Order Regarding Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2015-06-16016 June 2015 Compliance with March 12, 2012, NRC Order Regarding Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) Project stage: Other AEP-NRC-2015-83, Revision 1 of Final Integrated Plan Regarding March 12, 2012, NRC Order Regarding Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2015-10-0101 October 2015 Revision 1 of Final Integrated Plan Regarding March 12, 2012, NRC Order Regarding Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) Project stage: Other ML15264A8512015-11-0909 November 2015 Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 Project stage: Approval 2014-12-16
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Category:Drawing
MONTHYEARML22340A1522022-11-30030 November 2022 1 to Updated Final Safety Analysis Report, Chapter 5, Figures (Redacted) ML22340A1342022-11-30030 November 2022 1 to Updated Final Safety Analysis Report, Chapter 10, Figures ML22340A1912022-11-30030 November 2022 1 to Updated Final Safety Analysis Report, Chapter 8, Figures ML22340A2152022-11-30030 November 2022 1 to Updated Final Safety Analysis Report, Chapter 1, Figures (Redacted) ML22340A1692022-11-30030 November 2022 1 to Updated Final Safety Analysis Report, Chapter 14.3, Figures 14.3.4-1 to 14.3.4-158 (Unit 2) ML22340A1942022-11-30030 November 2022 1 to Updated Final Safety Analysis Report, Chapter 4, Figures ML22340A1442022-11-30030 November 2022 1 to Updated Final Safety Analysis Report, Chapter 14.4, Figures 14.4.2-1 to 14.4.9-2 (Unit 2) ML22340A1422022-11-30030 November 2022 1 to Updated Final Safety Analysis Report, Chapter 3, Figures (Unit 1) ML22340A1842022-11-30030 November 2022 1 to Updated Final Safety Analysis Report, Chapter 14.3, Figure 14.3.7-1 (Unit 2) ML22340A1382022-11-30030 November 2022 1 to Updated Final Safety Analysis Report, Chapter 11, Figure ML22340A1872022-11-30030 November 2022 1 to Updated Final Safety Analysis Report, Chapter 14.A-G, Figures 14.G-1 and 14.G-2 (Unit 1) ML22340A1892022-11-30030 November 2022 1 to Updated Final Safety Analysis Report, Chapter 9, Figures ML22340A1292022-11-30030 November 2022 1 to Updated Final Safety Analysis Report, Chapter 6, Figures ML21125A4882021-04-19019 April 2021 0 to Updated Final Safety Analysis Report, Chapter 14.1, Figures 14.1.0-1 to 14.1.12-2 (Unit 2) ML21125A5832021-04-19019 April 2021 0 to Updated Final Safety Analysis Report, Chapter 14.3, Figures 14.3.4-76 to 14.3.9-25 (Unit 1) ML21125A5672021-04-19019 April 2021 0 to Updated Final Safety Analysis Report, Chapter 9, Figures ML21125A5462021-04-19019 April 2021 0 to Updated Final Safety Analysis Report, Chapter 14.2, Figures 14.2.5-1 to 14.2.8-8 (Unit 2) ML21125A5792021-04-19019 April 2021 0 to Updated Final Safety Analysis Report, Chapter 3, Figures (Unit 2) ML21125A5032021-04-19019 April 2021 0 to Updated Final Safety Analysis Report, Chapter 14.4, Figures 14.4.2-1 to 14.4.9-2 (Unit 2) ML21125A5182021-04-19019 April 2021 0 to Updated Final Safety Analysis Report, Chapter 2, Figures ML21125A5352021-04-19019 April 2021 0 to Updated Final Safety Analysis Report, Chapter 1, Figures (Redacted) ML21125A4822021-04-19019 April 2021 0 to Updated Final Safety Analysis Report, Chapter 6, Figures ML21125A5252021-04-19019 April 2021 0 to Updated Final Safety Analysis Report, Chapter 14.2, Figures 14.2.5-1 to 14.2.7-6 (Unit 1) ML21125A5702021-04-19019 April 2021 0 to Updated Final Safety Analysis Report, Chapter 14.3, Figures 14.3.1-1A to 14.3.4-75 (Unit 1) ML21125A5432021-04-19019 April 2021 0 to Updated Final Safety Analysis Report, Chapter 14, Figures 14.1-1 to 14.1.13-6 (Unit 1) ML21125A5942021-04-19019 April 2021 0 to Updated Final Safety Analysis Report, Chapter 14.A-G, Figures 14.G-1 and 14.G-2 (Unit 1) ML21125A5332021-04-19019 April 2021 0 to Updated Final Safety Analysis Report, Chapter 14.3, Figure 14.3.7-1 (Unit 2) ML21125A4562021-04-19019 April 2021 0 to Updated Final Safety Analysis Report, Chapter 3, Figures (Unit 1) ML21125A5242021-04-19019 April 2021 0 to Updated Final Safety Analysis Report, Chapter 10, Figures ML21125A5692021-04-19019 April 2021 0 to Updated Final Safety Analysis Report, Chapter 14.3, Figures 14.3.4-1 to 14.3.4-158 (Unit 2) ML21125A5642021-04-19019 April 2021 0 to Updated Final Safety Analysis Report, Chapter 4, Figures ML21125A4752021-04-19019 April 2021 0 to Updated Final Safety Analysis Report, Chapter 5, Figures (Redacted) ML21125A5092021-04-19019 April 2021 0 to Updated Final Safety Analysis Report, Chapter 11, Figures ML18220A6192018-08-0808 August 2018 Figure 8.3-4, Amendment 5, Existing Soil Profiles Section D-D, Boring Location Plan, Looking East ML18220A6292018-08-0808 August 2018 Figure 3.2.3-6, Upper Core Support Assembly. 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Cook Nuclear Plant, Units 1 & 2, Revision 27 to Updated Final Safety Analysis Report, Chapter 8, Figure 8.3-1, Vital Instrument Bus Distribution System ML16343A0482016-10-24024 October 2016 Donald C. Cook Nuclear Plant, Units 1 & 2, Revision 27 to Updated Final Safety Analysis Report, Chapter 11, Figure 11.1-2B, Wds Liquids & Solids, Units No. 1 & 2, Sheet 3 of 3 2022-11-30
[Table view] Category:Letter type:AEP
MONTHYEARAEP-NRC-2024-01, Emergency Plan Revision 482024-01-0808 January 2024 Emergency Plan Revision 48 AEP-NRC-2023-56, Report Per Technical Specification 5.6.6 for Inoperability of Unit 1 Post Accident Monitoring Reactor Coolant (Loop 3 Cold Leg) Wide Range Temperature Recorder Thermal Sensor2023-12-20020 December 2023 Report Per Technical Specification 5.6.6 for Inoperability of Unit 1 Post Accident Monitoring Reactor Coolant (Loop 3 Cold Leg) Wide Range Temperature Recorder Thermal Sensor AEP-NRC-2023-45, Unit 2 - Schedular Exemption for Enhanced Weapons, Firearms, Background Checks, and Security Event Notifications Implementation2023-11-16016 November 2023 Unit 2 - Schedular Exemption for Enhanced Weapons, Firearms, Background Checks, and Security Event Notifications Implementation AEP-NRC-2023-40, Annual Report of Loss-of-Coolant Accident Evaluation Model Changes2023-08-29029 August 2023 Annual Report of Loss-of-Coolant Accident Evaluation Model Changes AEP-NRC-2023-34, Supplement to Request for Approval of Change Regarding Neutron Flux Instrumentation2023-08-0202 August 2023 Supplement to Request for Approval of Change Regarding Neutron Flux Instrumentation AEP-NRC-2023-29, Core Operating Limits Report2023-06-19019 June 2023 Core Operating Limits Report AEP-NRC-2023-32, Response to NRC Regulatory Issue Summary 2023-1 Preparation and Scheduling of Operator Licensing Examinations2023-06-0606 June 2023 Response to NRC Regulatory Issue Summary 2023-1 Preparation and Scheduling of Operator Licensing Examinations AEP-NRC-2023-33, Renewable Operating Permit2023-06-0505 June 2023 Renewable Operating Permit AEP-NRC-2023-30, Follow-Up Notification of Ph Non-Compliance for Turbine Room Sump2023-06-0101 June 2023 Follow-Up Notification of Ph Non-Compliance for Turbine Room Sump AEP-NRC-2023-27, Annual Radiological Environmental Operating Report2023-05-15015 May 2023 Annual Radiological Environmental Operating Report AEP-NRC-2023-19, Annual Radioactive Effluent Release Report2023-04-30030 April 2023 Annual Radioactive Effluent Release Report AEP-NRC-2023-23, Annual Report of Individual Monitoring for 20222023-04-24024 April 2023 Annual Report of Individual Monitoring for 2022 AEP-NRC-2023-24, Notification of Ph Non-Compliance for Turbine Room Sump2023-04-12012 April 2023 Notification of Ph Non-Compliance for Turbine Room Sump AEP-NRC-2023-20, Annual Report of Property Insurance2023-04-0303 April 2023 Annual Report of Property Insurance AEP-NRC-2023-15, Decommissioning Funding Status Report2023-03-28028 March 2023 Decommissioning Funding Status Report AEP-NRC-2023-11, Form OAR-1, Owner'S Activity Report2023-01-31031 January 2023 Form OAR-1, Owner'S Activity Report AEP-NRC-2023-02, Request for Approval of Change Regarding Neutron Flux Instrumentation2023-01-26026 January 2023 Request for Approval of Change Regarding Neutron Flux Instrumentation AEP-NRC-2022-66, Report Per Technical Specification 5.6.6 for Inoperability of Unit 2 Post Accident Monitoring Neutron Flux Monitoring2022-12-15015 December 2022 Report Per Technical Specification 5.6.6 for Inoperability of Unit 2 Post Accident Monitoring Neutron Flux Monitoring AEP-NRC-2022-46, Notification of Deviation from Electric Power Research Institute (EPRI) Materials Reliability Program 2019-008, Interim Guidance for NEI 03-08 Needed Requirements for Us PWR Plants for Management of Thermal Fatigue in2022-12-12012 December 2022 Notification of Deviation from Electric Power Research Institute (EPRI) Materials Reliability Program 2019-008, Interim Guidance for NEI 03-08 Needed Requirements for Us PWR Plants for Management of Thermal Fatigue in AEP-NRC-2022-61, Request for Relief Related to American Society of Mechanical Engineers (ASME) Code Case N-729-6 Supplemental Examination Requirements, ISIR-5-062022-10-24024 October 2022 Request for Relief Related to American Society of Mechanical Engineers (ASME) Code Case N-729-6 Supplemental Examination Requirements, ISIR-5-06 AEP-NRC-2022-58, U1C31 Steam Generator Tube Inspection Report2022-10-24024 October 2022 U1C31 Steam Generator Tube Inspection Report AEP-NRC-2022-56, Unit 2 - Transmittal of Report of Changes to the Emergency Plan2022-10-12012 October 2022 Unit 2 - Transmittal of Report of Changes to the Emergency Plan AEP-NRC-2022-30, Core Operating Limits Report2022-10-0606 October 2022 Core Operating Limits Report AEP-NRC-2022-51, Evacuation Time Estimate Analysis2022-08-31031 August 2022 Evacuation Time Estimate Analysis AEP-NRC-2022-50, Form OAR-1, Owner'S Activity Report2022-08-25025 August 2022 Form OAR-1, Owner'S Activity Report AEP-NRC-2022-35, Annual Report of Loss-of-Coolant Accident Evaluation Model Changes2022-08-18018 August 2022 Annual Report of Loss-of-Coolant Accident Evaluation Model Changes AEP-NRC-2022-47, Transmittal of Donald C. Cook Nuclear Plant, Emergency Plan, Revision 472022-08-0202 August 2022 Transmittal of Donald C. Cook Nuclear Plant, Emergency Plan, Revision 47 AEP-NRC-2022-42, Unit 2 Updated Steam Generator Tube Inspection Report to Reflect TSTF-577 Reporting Requirements2022-07-18018 July 2022 Unit 2 Updated Steam Generator Tube Inspection Report to Reflect TSTF-577 Reporting Requirements AEP-NRC-2022-29, Annual Radiological Environmental Operating Report for 20212022-05-13013 May 2022 Annual Radiological Environmental Operating Report for 2021 AEP-NRC-2022-15, CFR 72.48(d)(2) Summary Report of 10 CFR 72.48 Evaluations2022-05-0404 May 2022 CFR 72.48(d)(2) Summary Report of 10 CFR 72.48 Evaluations AEP-NRC-2022-28, 2021 Annual Radioactive Effluent Release Report2022-04-29029 April 2022 2021 Annual Radioactive Effluent Release Report AEP-NRC-2022-27, Annual Report of Individual Monitoring2022-04-27027 April 2022 Annual Report of Individual Monitoring AEP-NRC-2022-05, Application to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2022-04-0707 April 2022 Application to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements AEP-NRC-2022-18, Annual Report of Property Insurance2022-03-28028 March 2022 Annual Report of Property Insurance AEP-NRC-2022-20, Response to NRC Regulatory Issue Summary 2022-01 Preparation and Scheduling of Operator Licensing Examinations2022-03-14014 March 2022 Response to NRC Regulatory Issue Summary 2022-01 Preparation and Scheduling of Operator Licensing Examinations AEP-NRC-2022-12, Commitment Schedule Change Related to Seismic PRA Distributed Ignition Backup Power Source2022-03-0202 March 2022 Commitment Schedule Change Related to Seismic PRA Distributed Ignition Backup Power Source AEP-NRC-2022-02, Unit 2 - Supplement to Application to Revise Technical Specifications to Adopt TSTF-5, Revision 1, Revised Frequencies for Steam Generator Tube Inspections2022-02-0101 February 2022 Unit 2 - Supplement to Application to Revise Technical Specifications to Adopt TSTF-5, Revision 1, Revised Frequencies for Steam Generator Tube Inspections AEP-NRC-2022-01, Quality Assurance Program Change Request for Internal Audit Frequency2022-02-0101 February 2022 Quality Assurance Program Change Request for Internal Audit Frequency AEP-NRC-2022-03, Final Supplemental Response to NRC Generic Letter 2004-022022-01-20020 January 2022 Final Supplemental Response to NRC Generic Letter 2004-02 AEP-NRC-2021-68, Response to Request for Additional Information on Requested Change Regarding Containment Water Level Instrumentation2021-12-16016 December 2021 Response to Request for Additional Information on Requested Change Regarding Containment Water Level Instrumentation AEP-NRC-2021-67, Unit 2 - Decommissioning Funding Plan for Independent Spent Fuel Storage Installation2021-12-0909 December 2021 Unit 2 - Decommissioning Funding Plan for Independent Spent Fuel Storage Installation AEP-NRC-2021-66, 2020 Annual Radioactive Effluent Release Report Correction2021-11-17017 November 2021 2020 Annual Radioactive Effluent Release Report Correction AEP-NRC-2021-65, Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Cask2021-11-0808 November 2021 Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Cask AEP-NRC-2021-47, Unit 2 - Application to Revise Technical Specifications to Adopt TSTF-577, Revision 1, Revised Frequencies for Steam Generator Tube Inspections2021-11-0808 November 2021 Unit 2 - Application to Revise Technical Specifications to Adopt TSTF-577, Revision 1, Revised Frequencies for Steam Generator Tube Inspections AEP-NRC-2021-60, Registration of Dry Spent Fuel Storage Cask2021-10-12012 October 2021 Registration of Dry Spent Fuel Storage Cask AEP-NRC-2021-55, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Cask2021-09-20020 September 2021 Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Cask AEP-NRC-2021-48, Cycle 26 Core Operating Limits Report, Revision 02021-09-14014 September 2021 Cycle 26 Core Operating Limits Report, Revision 0 AEP-NRC-2021-53, Registration of Dry Spent Fuel Storage Cask2021-08-26026 August 2021 Registration of Dry Spent Fuel Storage Cask AEP-NRC-2021-50, Annual Report of Loss-of-Coolant Accident Evaluation Model Changes2021-08-25025 August 2021 Annual Report of Loss-of-Coolant Accident Evaluation Model Changes AEP-NRC-2021-44, Form OAR-1, Owner'S Activity Report2021-08-12012 August 2021 Form OAR-1, Owner'S Activity Report 2024-01-08
[Table view] Category:Status Report
MONTHYEARAEP-NRC-2023-15, Decommissioning Funding Status Report2023-03-28028 March 2023 Decommissioning Funding Status Report ML23044A3662023-02-15015 February 2023 Calendar Year 2022 Reactor Oversight Process Baseline Inspection Program Completion - Region III AEP-NRC-2015-16, Decommissioning Funding Status Report2015-03-20020 March 2015 Decommissioning Funding Status Report AEP-NRC-2015-13, Fourth Six-Month Status Report in Response to March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2015-02-25025 February 2015 Fourth Six-Month Status Report in Response to March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) AEP-NRC-2014-66, Third Six Month Status Report in Response to March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2014-08-27027 August 2014 Third Six Month Status Report in Response to March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) AEP-NRC-2014-16, Six Month Status Report in Response to March 12, 2012, Commission Order Modifying Licensees with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)2014-02-27027 February 2014 Six Month Status Report in Response to March 12, 2012, Commission Order Modifying Licensees with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) AEP-NRC-2014-17, Second Six Month Status Report in Response to March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events...2014-02-27027 February 2014 Second Six Month Status Report in Response to March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events... AEP-NRC-2013-72, 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)2013-08-26026 August 2013 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) ML1214500142012-05-23023 May 2012 NFPA 805 LAR Status Matrix - May 2012 AEP-NRC-2011-22, Submittal of Decommissioning Funding Status Report2011-03-30030 March 2011 Submittal of Decommissioning Funding Status Report ML0930902562009-11-0202 November 2009 Slides from Public Meeting - Unit 1 Cook Nuclear Plant Turbine Event Status Report ML0921803572009-08-21021 August 2009 July 2009 Report on the Status of Public Petitions Under Title 10 of the Code of Federal Regulations, Section 2.206, Enclosure ML0910301932009-03-30030 March 2009 Submittal of Decommissioning Funding Status Report ML0710002792007-03-30030 March 2007 Decommissioning Funding Status Report ML0509502522005-03-23023 March 2005 Decommissioning Funding Status Report ML0226002922002-09-17017 September 2002 Memorandum Regarding Report on the Status of Open TIAs Assigned to NRR ML0224601532002-08-29029 August 2002 Undated Document, Current Status of High Susceptibility Plants That May Receive Orders ML0224007982002-02-0101 February 2002 E-mail from Beth Wetzel Bulletin 2001-01 Status Report ML0224007922002-01-24024 January 2002 E-Mail from Allen Hiser to NRR Re Vhp Nozzle Status Report Update ML0224007872002-01-24024 January 2002 E-Mail from John Harrison to Jacob Zimmerman Re Vhp Nozzle Status Report Update ML0224007812002-01-18018 January 2002 E-mail from Jacob Zimmerman, Bulletin 2001-01 Status Report 2023-03-28
[Table view] |
Text
INDIANA Indiana Michigan Power MICHIGAN Cook Nuclear Plant POWER3 One Cook Place Bridgman, MI 49106 A unit ofAmerican Electric Power Indiana Michigan Powe r.cem August 26, 2013 AEP-NRC-2013-72 10 CFR 50.54(f)
Docket Nos.: 50-315 50-316 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Donald C. Cook Nuclear Plant Units 1 and 2 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)
References:
- 1. Letter from E. J. Leeds and M. R. Johnson, U. S. Nuclear Regulatory Commission (NRC) to All Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status, "Issuance of Order to Modify Licenses with Regard to Reliable Spent Fuel Pool Instrumentation," NRC Order Number EA-12-051, dated March 12, 2012, ML12054A682
- 2. NRC Interim Staff Guidance JLD-ISG-2012-03, Compliance with Order EA-12-051, Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation, Revision 0, dated August 29, 2012, ML12221A339
- 3. NEI 12-02, Industry Guidance for Compliance with NRC Order EA-12-051, "To Modify Licenses with Regard to Reliable Spent Fuel Pool Instrumentation", Revision 1, dated August 2012, ML12240A307
- 4. Letter from J. P. Gebbie, Indiana Michigan Power Company, to U. S. Nuclear Regulatory Commission, "Donald C. Cook Nuclear Plant Units 1 and 2, Initial Status Report in Response to March 12, 2012, Commission Order Modifying Licenses with Regard to Reliable Requirements for Reliable Spent Fuel Pool Instrumentation (Order Number EA 051)," AEP-NRC-2012-85, dated October 26, 2012, ML12312A473
- 5. Letter from J. P. Gebbie, Indiana Michigan Power Company, to U. S. Nuclear Regulatory Commission, "Donald C. Cook Nuclear Plant Unit 1 and Unit 2, Overall Integrated Plan in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)," dated February 27, 2013, ML13071A323.
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U. S. Nuclear Regulatory Commission AEP-NRC-2013-72 Page 2 On March 12, 2012, the Nuclear Regulatory Commission issued an order (Reference 1) to Indiana Michigan Power Company (I&M), the licensee for the Donald C. Cook Nuclear Plant (CNP) Units 1 and 2. Reference 1 was immediately effective and directed I&M to establish reliable spent fuel pool level instrumentation. Specific requirements are outlined in Attachment 2 of Reference 1.
Reference 1 required submission of an initial status report 60 days following issuance of the final interim staff guidance (Reference 2) and an overall integrated plan pursuant to Section IV, Condition C. Reference 2 endorses industry guidance document NEI 12-02, Revision 1 (Reference
- 3) with clarifications and exceptions identified in Reference 2. Reference 4 provided I&M's initial status report regarding mitigation strategies. Reference 5 provided I&M's overall integrated plan.
Reference 1 requires submission of a status report at six-month intervals following submittal of the overall integrated plan. Reference 3 provides direction regarding the content of the status reports.
The purpose of this letter is to provide the first six-month status report pursuant to Section IV, Condition C.2, of Reference 1, that delineates progress made in implementing the requirements of Reference 1. Enclosure 1 to this submittal provides an affirmation. Enclosure 2 provides an update of milestone accomplishments since the last status report, including any changes to the compliance method, schedule, or need for relief and the basis, if any.
This letter contains no new or revised regulatory commitments. Should you have any questions, please contact Mr. Michael K. Scarpello, Regulatory Affairs Manager, at (269) 466-2649.
Sincerely, Joel P. Gebbie Site Vice President DMB/kmh
Enclosure:
- 1. Affirmation
- 2. Indiana Michigan Power company's First Six month Status Report for the Implementation of Order EA-12-051, Order Modifying Licenses with Regard to Requirements for Reliable Spent Fuel Pool Instrumentation c: S. R. Jones, NRRPDSS/SBPB, NRC J. T. King, MPSC S. M. Krawec, AEP Ft. Wayne, w/o enclosure MDEQ - RMD/RPS NRC Resident Inspector C. D. Pederson, NRC Region III T. J. Wengert, NRC Washington DC
Enclosure 1 to AEP-NRC-2013-72 AFFIRMATION I, Joel P. Gebbie, being duly sworn, state that I am Site Vice President of Indiana Michigan Power Company (I&M), that I am authorized to sign and file this request with the Nuclear Regulatory Commission on behalf of I&M, and that the statements made and the matters set forth herein pertaining to I&M are true and correct to the best of my knowledge, information, and belief.
Indiana Michigan Power Company f4A Joel P. Gebbie Site Vice President SWORN TO AND SUBSCRIBED BEFORE ME THIS c.S DAY OF j-,2013 DANIELLE BURGOYNE Notary Public, State of Michigan County of Berrien My Commission Expires 04-04-2018 My Com Notaryeslic " Acting In the County fr My Commission Expires - -' - *-\
ENCLOSURE 2 TO AEP-NRC-2013-72 Indiana Michigan Power Company's First Six Month Status Report for the Implementation of Order EA-12-051, Order Modifying Licenses with Regard to Requirements for Reliable Spent Fuel Pool Instrumentation I Introduction Indiana Michigan Power Company (I&M), the licensee for Donald C. Cook Nuclear Plant (CNP),
developed an Overall Integrated Plan (OIP) (Reference 1 in Section 8), documenting the requirements to install reliable spent fuel pool (SFP) level instrumentation, in response to (Reference 2 in Section 8). This enclosure provides an update of milestone accomplishments since submittal of the OIP. There are no changes to the compliance method, schedule, or need for relief/relaxation at this time.
2 Milestone Accomplishments The following milestone(s) have been completed since the development of the OIP, and are current as of July 30, 2013.
- Commence Engineering Modification Design, order electronics - Engineering commenced on June 6, 2013, and electronics were ordered on July 2, 2013, by issuance of Purchase Order (PO) 01560122.
3 Milestone Schedule Status The following ýprovides an update to the milestone schedule to support the OIP. This section provides the activity status of each item, and the expected completion date noting any change.
The dates are planning dates subject to change as design and implementation details are developed.
The revised milestone target completion dates do not impact the order implementation date.
Target Revised Milestone Completion Activity Target Date Status Completion Date Date Submit 60 Day Status Report Oct 2012 Complete Submit OIP Feb 2013 Complete Unit refueling outage ( 1 st RFO) start March 2013 Outage Completed Submit 6 Month Updates:
Complete with Update 1 Aug 2013 this submittal Update 2 Feb 2014 Not Started Update 3 Aug 2014 Not Started to AEP-NRC-2013-72 Page 2 Revised Target Completion Activity Target Milestone Date Status Completion Date Update 4 Feb 2015 Not Started Modifications:
Commence Engineering Modification Commenced Design April 2013 Complete June 6, 2013 P0 issued Order Electronics April 2013 Complete July 2, 2013 Complete Design* December In Progress 2013 Receive electronics December Not Started April 2014 2013 Commence Installation June 2014 Not Started Complete functional test November Not Started 2014 Procedures:
Issue Maintenance Procedures August 2014 Not Started Training:
Implement Training September Not Started 2014 Submit Completion Report February 2015 Not Started 4 Changes to Compliance Method There are no changes to the compliance method as documented in the OIP.
5 Need for Relief/Relaxation and Basis for the Relief/Relaxation I&M expects to comply with the order implementation date and no relief/relaxation is required at this time.
6 Open Items from Overall Integrated Plan and Draft Safety Evaluation The following table provides a summary of the open items documented in the OIP as discussed in the Request for Additional Information (RAI) (Reference 6) and the subsequent RAI response (Reference 7) and the status of each item. Currently there is no Draft Safety Evaluation (SE).
to AEP-NRC-2013-72 Page 3 Overall Integrated Plan Open Item Status RAI-1 a) The specific functional reasons for identification Complete. Response (Ref 6) of the elevation of Level 1. Specify how the submitted July 11, 2013 identified elevation represents the HIGHER of (Reference 7) the two points described in the NEI 12-02 guidance for this level.
b) Provide a clearly labeled sketch depicting the Complete. Sketch attached to elevation view of the proposed typical mounting this enclosure as Figure 1.
arrangement for the portions of instrument channel consisting of permanent measurement channel equipment (e.g., fixed level sensors and/or stilling wells, and mounting brackets).
Indicate on this sketch the datum values representing Level 1, Level 2, and Level 3, as well as the top of the fuel. Indicate on this sketch the portion of the level sensor measurement range that is sensitive to measurement of the fuel pool level, with respect to the Level 1, Level 2, and Level 3 datum points.
c) The OIP refers to drawings 12-3801, Complete. Response OP-12-5136, and DC-06033. Provide these submitted July 11, 2013 drawings and, if they do not provide the (Reference 7) necessary information requested in this RAI, please provide additional drawinqs.
RAI-2 Please provide a clearly labeled sketch or Sketches attached to this (Ref 6) marked-up plant drawing of the plan view of the enclosure as Figure 2 and SFP area, depicting the inside dimensions, the Figure 3 planned locations / placement of the primary and back-up level sensors, and the proposed routing of the cables that will extend from the sensors toward the location of the read-out/display device.
RAI-3 a) The design criteria that will be used to estimate CNP plans to provide this (Ref 6) the total loading on the mounting device(s), information in the February including static weight loads and dynamic 2014 update.
loads. Describe the methodology that will be used to estimate the total loading, inclusive of design basis maximum seismic loads and the hydrodynamic loads that could result from pool sloshing or other effects that could accompany such seismic forces.
to AEP-NRC-2013-72 Page 4 Overall Integrated Plan Open Item Status b) A description of the manner in which the level CNP plans to provide this sensor (and stilling well, if appropriate) will be information in the February attached to the refueling roof and/or other 2014 update.
support structures for each planned point of attachment of the probe assembly. Indicate in a drawing the portions of the level sensor that will serve as points of attachment for mechanical/mounting and electrical connections.
c) A description of the manner by which the CNP plans to provide this mechanical connections will attach the level information in the February instrument to permanent SFP structures so as 2014 update.
to support the level sensor assembly.
i RAI-4 a) A description of the specific method or CNP plans to provide this (Ref 6) combination of methods that will be applied to information in the February demonstrate the reliability of the permanently 2014 update.
installed equipment under Beyond Design Basis (BDB) ambient temperature, humidity, shock, vibration, and radiation conditions.
b) A description of the testing and/or analyses that CNP plans to provide this will be conducted to provide assurance that the information in the February equipment will perform reliably under the worst- 2014 update.
case credible design basis loading at the location where the equipment will be mounted.
Include a discussion of this seismic reliability demonstration as it applies to: 1) the level sensor mounted in the SFP area, and 2) any control boxes, electronics, or read-out and re-transmitting devices that will be employed to convey the level information from the level sensor to the plant operators or emergency responders.
c) A description of the specific method or CNP plans to provide this combination of methods that will be used to information in the February confirm the reliability of the permanently 2014 update.
installed equipment such that, following a seismic event, the instrument will maintain its required accuracy.
RAI-5 a) A description of how the two channels of the CNP plans to provide this (Ref 6) proposed level measurement system meet this information in the February requirement so that the potential for a common 2014 update.
cause event to adversely affect both channels is minimized to the extent practicable.
to AEP-NRC-2013-72 Page 5 Overall Integrated Plan Open Item Status b) Further information on how each level CNP plans to provide this measurement system, consisting of level information in the February sensor electronics, cabling, and readout 2014 update.
devices will be designed and installed to address independence through the application and selection of independent power sources, independence of signals sent to the location(s) of the readout devices, and the independence of the displays.
RAI-6 a) If the level measurement channels are to be CNP plans to provide this (Ref 6) powered through a battery system (either information in the February directly or through an Uninterruptible Power 2014 update.
Supply), provide the design criteria that will be applied to size the battery in a manner that ensures, with margin, that the channel will be available to run reliably and continuously following the onset of the BDB event for the minimum duration needed, consistent with the plant mitigation strategies for BDB external events (Order EA-12-049).
b) The location where the batteries will be located, CNP plans to provide this indicating the accessibility, and the distance information in the February from the related instrument display. 2014 update.
RAI-7 a) An estimate of the expected instrument CNP plans to provide this (Ref 6) channel accuracy performance (e.g., in percent information in the February of span) under both: 2014 update.
- 1) normal SFP level conditions (approximately Level 1 or higher), and
- 2) at the BDB conditions (i.e., radiation, temperature, humidity, post-seismic and post-shock conditions) that would be present if the SFP level were at the Level 2 and Level 3 datum points.
b) A description of the methodology that will be CNP plans to provide this used for determining the maximum allowed information in the February deviation from the instrument channel design 2014 update.
accuracy that will be employed under normal operating conditions as an acceptance criterion for a calibration procedure to flag to operators and to technicians that the channel requires adjustment to within the normal condition design accuracy.
to AEP-NRC-2013-72 Page 6 Overall Integrated Plan Open Item Status RAI-8 a) A description of the capability and provisions CNP plans to provide this (Ref 6) the proposed level sensing equipment will have information in the February to enable periodic testing and calibration, 2014 update.
including how this capability enables the equipment to be tested in-situ.
b) A description how such testing and calibration CNP plans to provide this will enable the conduct of regular channel information in the February checks of each independent channel against 2014 update.
the other, and against any other permanently-installed SFP level instrumentation.
c) A description of the calibration and functional CNP plans to provide this checks that will be performed, the frequency at information in the February which they will be conducted with a discussion 2014 update.
on the measures taken to detect when the instrumentation is operable but degraded, and how these surveillances will be incorporated into the plant surveillance program.
d) A description of the preventative maintenance CNP plans to provide this tasks required to be performed during normal information in the February operation, and the planned maximum 2014 update.
surveillance interval that is necessary to ensure that the channels are fully conditioned to accurately and reliably perform their functions when needed.
RAI-9 a) The specific location for the primary and Complete. One instrument (Ref 6) backup instrument channel display. channel display is located in the Unit 1 control room; the second channel display is located in the Unit 2 control room. The channels are identical, and both are suitable for a primary or backup function.
b) If the primary or backup display location is Complete. One instrument other than the main control room, then provide channel display is located in justification for prompt accessibility to displays the Unit 1 control room, the including primary and alternate route second channel display is evaluation, habitability at display location(s), located in the Unit 2 control continual resource availability for personnel room, no additional justification responsible to promptly read displays, and is required.
provisions for communications with decision-makers for the various SFP drain-down scenarios and external events.
to AEP-NRC-2013-72 Page 7 Overall Integrated Plan Open Item Status c) The reasons justifying why the locations Complete. Both control rooms selected enable the information from these will be manned during normal, instruments to be considered "promptly event, and post-event accessible" to various drain-down scenarios conditions and will facilitate and external events. display observation during normal operation and during implementation of post-event FLEX strategies.
RAI-10 Please provide the following: A list of the CNP plans to provide this (Ref 6) operating (both normal and abnormal information in the February response) procedures, calibration/test 2014 update.
procedures, maintenance procedures, and inspection procedures that will be developed for use of the spent fuel pool instrumentation in a manner that addresses the Order requirements. Please include a brief description of the specific technical objectives to be achieved within each procedure. If your plan incorporates the use of portable spent fuel level monitoring components, please include a description of the objectives to be achieved with regard to the storage location and provisions for installation of the portable components, when needed.
RAI-1 1 a) Further information describing the maintenance CNP plans to provide this (Ref 6) and testing program the licensee will establish information in the February and implement to ensure that regular testing 2014 update.
and calibration is performed and verified by inspection and audit to demonstrate conformance with design and system readiness requirements. Include a description of your plans for ensuring that necessary channel checks, functional tests, periodic calibration, and maintenance will be conducted for the level measurement system and its supporting equipment.
b) A description of how the guidance in CNP plans to provide this NEI 12-02, Section 4.3, regarding information in the February compensatory actions for one or both non- 2014 update.
functioning channels will be addressed.
c) A description of what compensatory actions are CNP plans to provide this planned in the event that one of the instrument information in the February channels cannot be restored to functional 2014 update.
status within 90 days.
to AEP-NRC-2013-72 Page 8 Draft Safety Evaluation Open Item Status None 7 Potential Draft Safety Evaluation Impacts CNP has not yet received a Draft Safety Evaluation; therefore, no potential impacts can be determined.
8 References The following references support the updates to the OIP described in this attachment.
- 1. I&M's Overall Integrated Plan in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA 051)," dated February 27, 2013 (AEP-NRC-2013-14).
- 2. NRC Order Number EA-12-051, "Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation," dated March 12, 2012.
- 3. Sargent & Lundy Project No. 12105-405 Notes of Meeting, "Spent Fuel Pool Level Conceptual Design Kick-off - June 6, 2013."
- 4. I&M Purchase Order (PO) 01560122 issued July 2, 2013 to Mohr Test and Measurement LLC.
- 5. I&M EC-52892 "Conceptual Design - Spent Fuel Pool Level for NRC Order EA-12-051".
- 6. Letter from Thomas J. Wengert, NRC, to Lawrence J. Weber, I&M, "Donald C. Cook Nuclear Plant, Units 1 and 2 - Request for Additional Information on the Overall Integrated Plan in Response to Order EA-12-051 Concerning Reliable Spent Fuel Pool Instrumentation (TAC Nos. MF0761 and MF0762)," dated June 19, 2013 (ADAMS Accession No. ML13164A381).
- 7. Donald C. Cook Nuclear Plant Units 1 and 2 Response to Request for Additional Information Regarding the Overall Integrated Plan in Response to Order EA-12-051, "Issuance of Order to Modify Licenses with Regard to Reliable Spent Fuel Pool Instrumentation", dated July 11, 2013 (AEP-NRC-2013-57).
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THIS PAGE IS AN OVERSIZED DRAWING OR FIGURE, THAT CAN BE VIEWED AT THE RECORD TITLED:
Figure 3 Enclosure To AEP-NRC-3013-72 WITHIN THIS PACKAGE... OR, BY SEARCHING USING THE DOCUMENT/REPORT D-02X