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| | issue date = 12/16/2014 | | | issue date = 12/16/2014 |
| | title = Update to Communications Assessment Implementation Actions and Timeline - Fukushima Dai-ichi Near-Term Task Force Recommendation 9.3, Emergency Preparedness | | | title = Update to Communications Assessment Implementation Actions and Timeline - Fukushima Dai-ichi Near-Term Task Force Recommendation 9.3, Emergency Preparedness |
| | author name = Gebbie J P | | | author name = Gebbie J |
| | author affiliation = American Electric Power, Indiana Michigan Power Co | | | author affiliation = American Electric Power, Indiana Michigan Power Co |
| | addressee name = | | | addressee name = |
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| : 3. Letter from P. S. Tam, NRC, to L. J. Weber, I&M, "Donald C. Cook Nuclear Plant, Units 1 and 2 -Review of 60-Day Response to Request for Information Regarding Recommendation 9.3 of the Near-Term Task Force Related to the Fukushima Dai-ichi Nuclear Power Plant Accident (TAC Nos. ME8683 and ME8684)," dated June 8, 2012, ADAMS Accession No. ML12145A640. | | : 3. Letter from P. S. Tam, NRC, to L. J. Weber, I&M, "Donald C. Cook Nuclear Plant, Units 1 and 2 -Review of 60-Day Response to Request for Information Regarding Recommendation 9.3 of the Near-Term Task Force Related to the Fukushima Dai-ichi Nuclear Power Plant Accident (TAC Nos. ME8683 and ME8684)," dated June 8, 2012, ADAMS Accession No. ML12145A640. |
| U. S. Nuclear Regulatory Commission EP-NRC-2014-91 Page 2 4. Letter from M. H. Carlson, I&M, to the NRC, "Donald C. Cook Nuclear Plant Units 1 and 2, Communications Assessment Requested by Nuclear Regulatory Commission Letter,'Request for Information Pursuant to Title 10 of the Code of Federal Regulations 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,' | | U. S. Nuclear Regulatory Commission EP-NRC-2014-91 Page 2 4. Letter from M. H. Carlson, I&M, to the NRC, "Donald C. Cook Nuclear Plant Units 1 and 2, Communications Assessment Requested by Nuclear Regulatory Commission Letter,'Request for Information Pursuant to Title 10 of the Code of Federal Regulations 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,' |
| dated March 12, 2012," AEP-NRC-2012-83, dated October 31, 2012, ADAMS Accession No. ML1 2318A1 76.5. Letter from T. J. Wengert, NRC, to L. J. Weber, I&M, " Donald C. Cook Nuclear Plant, Units 1 And 2 -Staff Assessment in Response to Recommendation 9.3 of The Near Term Task Force Related to the Fukushima Dai-ichi Nuclear Power Plant Accident (TAC Nos. ME9950 and ME9951)," dated June 6, 2013, ADAMS Accession No. ML 13148A294. | | dated March 12, 2012," AEP-NRC-2012-83, dated October 31, 2012, ADAMS Accession No. ML12318A176.5. Letter from T. J. Wengert, NRC, to L. J. Weber, I&M, " Donald C. Cook Nuclear Plant, Units 1 And 2 -Staff Assessment in Response to Recommendation 9.3 of The Near Term Task Force Related to the Fukushima Dai-ichi Nuclear Power Plant Accident (TAC Nos. ME9950 and ME9951)," dated June 6, 2013, ADAMS Accession No. ML13148A294. |
| By Reference 1, the U. S. Nuclear Regulatory Commission (NRC) requested that licensees provide an assessment of their current communications systems and equipment used during an emergency event to identify any enhancements that may be needed to ensure communications are maintained during a large scale natural event resulting in a loss of all alternating current power. By Reference 2, Indiana Michigan Power Company (I&M) provided a response to the Reference 1 Request for Information. | | By Reference 1, the U. S. Nuclear Regulatory Commission (NRC) requested that licensees provide an assessment of their current communications systems and equipment used during an emergency event to identify any enhancements that may be needed to ensure communications are maintained during a large scale natural event resulting in a loss of all alternating current power. By Reference 2, Indiana Michigan Power Company (I&M) provided a response to the Reference 1 Request for Information. |
| I&M's response proposed an alternative course of action and estimated completion date for the Donald C. Cook Nuclear Plant (CNP), Unit 1 and Unit 2. By Reference 3, the NRC approved the alternative course of action. By Reference 4, I&M transmitted the communication assessment performed in accordance with the approved alternative. | | I&M's response proposed an alternative course of action and estimated completion date for the Donald C. Cook Nuclear Plant (CNP), Unit 1 and Unit 2. By Reference 3, the NRC approved the alternative course of action. By Reference 4, I&M transmitted the communication assessment performed in accordance with the approved alternative. |
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| ==Enclosures:== | | ==Enclosures:== |
| : 1. Affirmation | | : 1. Affirmation |
| : 2. Updated Implementation Timeline c: M. L. Chawla, NRC Washington, DC J. T. King, MPSC, w/o enclosures E. J. Leeds, NRR, NRC MDEQ -RMD/RPS NRC Resident Inspector C. D. Pederson, NRC Region III A. J. Williamson, AEP Ft. Wayne, w/o enclosures Enclosure 1 to AEP-NRC-2014-91 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 document with the U. S.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 Joel P. Gebbie Site Vice President SWORN TO AND SUBSCRIBED BEFORE ME THIS JL4DAY OF ý_.Pp r-j C h , 2014 MC s Notan Public My Commission Expires r3 Il \g Enclosure 2 to AEP-NRC-2014-91 Updated Implementation Timeline Enclosure 2 to AEP-NRC-2014-91 Page 1 The following table provides an updated status for the Donald C. Cook Nuclear Plant (CNP) Communication Assessment recommended enhancements presented in Enclosure 3, "Communications Assessment Implementation Timeline," of the letter from M. H. Carlson, Indiana Michigan Power Company (I&M), to U. S. Nuclear Regulatory Commission (NRC), dated October 31, 2012, Agencywide Documents Access Management Systems Accession No. ML1 2318A1 76.Communications Assessment Implementation Timeline Recommendation Stated in I&M Letter Updated Status dated October 31, 2012 Updated Status Supplement direct telephone lines linking Complete as Stated -Satellite phones are available to provide offsite communication. | | : 2. Updated Implementation Timeline c: M. L. Chawla, NRC Washington, DC J. T. King, MPSC, w/o enclosures E. J. Leeds, NRR, NRC MDEQ -RMD/RPS NRC Resident Inspector C. D. Pederson, NRC Region III A. J. Williamson, AEP Ft. Wayne, w/o enclosures Enclosure 1 to AEP-NRC-2014-91 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 document with the U. S.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 Joel P. Gebbie Site Vice President SWORN TO AND SUBSCRIBED BEFORE ME THIS JL4DAY OF ý_.Pp r-j C h , 2014 MC s Notan Public My Commission Expires r3 Il \g Enclosure 2 to AEP-NRC-2014-91 Updated Implementation Timeline Enclosure 2 to AEP-NRC-2014-91 Page 1 The following table provides an updated status for the Donald C. Cook Nuclear Plant (CNP) Communication Assessment recommended enhancements presented in Enclosure 3, "Communications Assessment Implementation Timeline," of the letter from M. H. Carlson, Indiana Michigan Power Company (I&M), to U. S. Nuclear Regulatory Commission (NRC), dated October 31, 2012, Agencywide Documents Access Management Systems Accession No. ML12318A176.Communications Assessment Implementation Timeline Recommendation Stated in I&M Letter Updated Status dated October 31, 2012 Updated Status Supplement direct telephone lines linking Complete as Stated -Satellite phones are available to provide offsite communication. |
| the CNP Emergency Facilities to the The satellite phones are periodically checked to assure their availability for Berrien County Emergency Operations communication among key emergency response functions including the BCEOC, the Center (BCEOC) with satellite phones for Lake Township Fire Department, the Emergency Operations Facility (EOF), the the postulated loss of the public phone Technical Support Center (TSC), offsite survey teams, onsite survey teams, security, system infrastructure, and the Shift Manager complex.Evaluate capabilities of offsite radio communications including: | | the CNP Emergency Facilities to the The satellite phones are periodically checked to assure their availability for Berrien County Emergency Operations communication among key emergency response functions including the BCEOC, the Center (BCEOC) with satellite phones for Lake Township Fire Department, the Emergency Operations Facility (EOF), the the postulated loss of the public phone Technical Support Center (TSC), offsite survey teams, onsite survey teams, security, system infrastructure, and the Shift Manager complex.Evaluate capabilities of offsite radio communications including: |
| : 1. Verifying the ability of existing 450 Complete as Modified -As noted above, satellite phones are available to provide Megahertz (MHz) trunked radios to offsite communication. | | : 1. Verifying the ability of existing 450 Complete as Modified -As noted above, satellite phones are available to provide Megahertz (MHz) trunked radios to offsite communication. |
Letter Sequence Other |
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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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Cook - Revision 1, Change 0 to RMT-2080-EOF-001, Activation and Operation of the Eof. 2016-07-11
[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
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INDIAN_ Indiana Michigan Power MICHIGAN Cook Nuclear Plant POWER One Cook Place Bridgman, MI 49106 A unit of American Electric Power India naMichigan Power.com December 16, 2014 AEP-NRC-2014-91 10 CFR 50.54(f)Docket No.: 50-315 50-316 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk 11555 Rockville Pike Rockville, MD 20852 Donald C. Cook Nuclear Plant Units 1 and 2 Update to Communications Assessment Implementation Actions and Timeline -Fukushima Dai-ichi Near-Term Task Force Recommendation 9.3, "Emergency Preparedness"
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, "Request for Information Pursuant to Title 10 of the Code of Federal Regulations 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," dated March 12, 2012, Agencywide Documents Access Management Systems (ADAMS) Accession No. ML12056A046.
- 2. Letter from J. P. Gebbie, Indiana Michigan Power Company (A&M), to NRC, "60-Day Response to NRC Letter, Request for Information Pursuant to Title 10 of the Code of Federal Regulations 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; dated March 12, 2012," AEP-NRC-2012-34, dated May 11, 2012, ADAMS Accession No. ML12142A110.
- 3. Letter from P. S. Tam, NRC, to L. J. Weber, I&M, "Donald C. Cook Nuclear Plant, Units 1 and 2 -Review of 60-Day Response to Request for Information Regarding Recommendation 9.3 of the Near-Term Task Force Related to the Fukushima Dai-ichi Nuclear Power Plant Accident (TAC Nos. ME8683 and ME8684)," dated June 8, 2012, ADAMS Accession No. ML12145A640.
U. S. Nuclear Regulatory Commission EP-NRC-2014-91 Page 2 4. Letter from M. H. Carlson, I&M, to the NRC, "Donald C. Cook Nuclear Plant Units 1 and 2, Communications Assessment Requested by Nuclear Regulatory Commission Letter,'Request for Information Pursuant to Title 10 of the Code of Federal Regulations 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,'
dated March 12, 2012," AEP-NRC-2012-83, dated October 31, 2012, ADAMS Accession No. ML12318A176.5. Letter from T. J. Wengert, NRC, to L. J. Weber, I&M, " Donald C. Cook Nuclear Plant, Units 1 And 2 -Staff Assessment in Response to Recommendation 9.3 of The Near Term Task Force Related to the Fukushima Dai-ichi Nuclear Power Plant Accident (TAC Nos. ME9950 and ME9951)," dated June 6, 2013, ADAMS Accession No. ML13148A294.
By Reference 1, the U. S. Nuclear Regulatory Commission (NRC) requested that licensees provide an assessment of their current communications systems and equipment used during an emergency event to identify any enhancements that may be needed to ensure communications are maintained during a large scale natural event resulting in a loss of all alternating current power. By Reference 2, Indiana Michigan Power Company (I&M) provided a response to the Reference 1 Request for Information.
I&M's response proposed an alternative course of action and estimated completion date for the Donald C. Cook Nuclear Plant (CNP), Unit 1 and Unit 2. By Reference 3, the NRC approved the alternative course of action. By Reference 4, I&M transmitted the communication assessment performed in accordance with the approved alternative.
The communication assessment identified recommendations to further evaluate or enhance the CNP communications capabilities, and identified actions to be evaluated as part of the mitigation strategies for beyond design basis events. Enclosure 3 of Reference 4 provided an implementation timeline for the recommended evaluations and enhancements.
Reference 5 transmitted an NRC Safety Assessment which included a review of the enhancements.
The Safety Assessment documented the NRC staff's conclusion that the enhancements, in conjunction with other communication system attributes, would help ensure that communications are maintained.
As tabulated in Enclosure 2 to this letter, I&M has either completed the recommended communications enhancement or determined that the enhancement is not needed. I&M considers that the conclusion documented in Reference 5 remains valid.Enclosure 1 to this letter provides an affirmation.
Enclosure 2 provides the updated enhancement implementation timeline.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 JRW/amp U. S. Nuclear Regulatory Commission EP-NRC-2014-91 Page 3
Enclosures:
- 1. Affirmation
- 2. Updated Implementation Timeline c: M. L. Chawla, NRC Washington, DC J. T. King, MPSC, w/o enclosures E. J. Leeds, NRR, NRC MDEQ -RMD/RPS NRC Resident Inspector C. D. Pederson, NRC Region III A. J. Williamson, AEP Ft. Wayne, w/o enclosures Enclosure 1 to AEP-NRC-2014-91 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 document with the U. S.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 Joel P. Gebbie Site Vice President SWORN TO AND SUBSCRIBED BEFORE ME THIS JL4DAY OF ý_.Pp r-j C h , 2014 MC s Notan Public My Commission Expires r3 Il \g Enclosure 2 to AEP-NRC-2014-91 Updated Implementation Timeline Enclosure 2 to AEP-NRC-2014-91 Page 1 The following table provides an updated status for the Donald C. Cook Nuclear Plant (CNP) Communication Assessment recommended enhancements presented in Enclosure 3, "Communications Assessment Implementation Timeline," of the letter from M. H. Carlson, Indiana Michigan Power Company (I&M), to U. S. Nuclear Regulatory Commission (NRC), dated October 31, 2012, Agencywide Documents Access Management Systems Accession No. ML12318A176.Communications Assessment Implementation Timeline Recommendation Stated in I&M Letter Updated Status dated October 31, 2012 Updated Status Supplement direct telephone lines linking Complete as Stated -Satellite phones are available to provide offsite communication.
the CNP Emergency Facilities to the The satellite phones are periodically checked to assure their availability for Berrien County Emergency Operations communication among key emergency response functions including the BCEOC, the Center (BCEOC) with satellite phones for Lake Township Fire Department, the Emergency Operations Facility (EOF), the the postulated loss of the public phone Technical Support Center (TSC), offsite survey teams, onsite survey teams, security, system infrastructure, and the Shift Manager complex.Evaluate capabilities of offsite radio communications including:
- 1. Verifying the ability of existing 450 Complete as Modified -As noted above, satellite phones are available to provide Megahertz (MHz) trunked radios to offsite communication.
Therefore, the 450 Mhz portable radios need not be part of a function in "point-to-point" mode. trunked radio system. However, these radios do have the capability of communicating point-to-point.
- 2. Mapping of radio reception in the Not Needed -As noted above, satellite phones are available to provide offsite Emergency Planning Zone (EPZ) and communication.
Therefore, mapping of radio reception in the EPZ and to the to the Emergency Operation Centers Emergency Operation Centers without the repeater in service is not necessary to without the repeater in service. support the FLEX strategies.
- 3. Assuring the survivability for the offsite Not Needed -As noted above, satellite phones are available to provide offsite radio repeater and antennae, communication.
Therefore, the offsite repeater and antennae need not be survivable for all Beyond Design Basis External Events (BDBEE) to support the diverse and flexible mitigation (FLEX) strategies.
Enclosure 2 to AEP-NRC-2014-91 Page 2-Communications Assessment Implementation Timeline Recommendation Stated in I&M Letter dated October 31, 2012 Updated Status Determine feasibility for the following future actions associated with FLEX: 1. Provide additional battery backup for the Public Address (PA) system.2. Provide capability for hooking alternate power generator for intra-plant 450 MHz radio system.up the Not Needed -The PA system receives power from the Critical Control Room Power Supply (CCRP). In the event of an extended loss of alternating current (AC) power (ELAP) condition, the CCRP will automatically switch to a backup battery reserve capable of 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> operation.
The FLEX validation process determined that power can be restored to the battery chargers within 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> and 35 minutes, using the 600 volts alternating current (VAC), 500 kilowatts (kW) portable diesel generator (DG). Therefore, additional battery backup is not needed to support the FLEX strategies.
Not Needed -The stated action referred to the radio system normally used for day-to-day plant operation.
The FLEX strategies rely on separate dedicated FLEX radios served by Portable Tactical Repeaters (PTR) and Bi-Directional Amplifiers (BDA) which would be deployed at strategic locations in the plant. This would provide radio coverage to the expected response areas without reliance on the radio system normally used for day to day plant operation.
The PTRs and BDAs are powered by batteries to ensure operability during an ELAP event. There are battery chargers located in the FLEX Storage Building.
Procedure 1-OHP-4027-FSG-501, "FLEX Equipment Staging" includes the deployment of a DG to provide power to the battery charging stations.
Therefore, the capability for hooking up alternate power generator for the intra-plant 450 MHz radio system is not needed to support the FLEX strategies Enclosure 2 to AEP-NRC-2014-91 Page 3 Communications Assessment Implementation Timeline Recommendation Stated in I&M Letter Updated Status dated October 31, 2012 Updated Status 3. Provide capability for hooking up Complete as Stated -As noted above, the PA system receives power from the alternate power generator for the PA CCRP which will be automatically switched over to a backup battery reserve capable system. of 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> operation in the event of an ELAP. As also noted above, the 600 VAC, 500 kW portable DG can be used to provide power to the battery chargers within the 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> period.4. Harden exterior antennae to the extent Not Needed -The FLEX communication strategy does not rely on the existing necessary to provide reasonable exterior antenna. The deployment of PTRs and BDAs as described above will assure assurance of survivability, adequate in plant radio communication.
Therefore, the hardening of the exterior antennae is not needed to support the FLEX strategies.
- 5. Provide survivable offsite 450 MHz Not Needed -The offsite repeater and antennae may not be survivable for all radio system (including repeater and BDBEEs. However, as described above, satellite phones will be available to provide antennae) or portable repeater offsite communication.
Therefore the offsite repeater and antennae need not be equipment.
survivable for all BDBEEs to support the FLEX strategies.
Provide alternate power supplies for the following locations (assuming survivability) at a minimum: 1. The EOF, which also has an existing Not Needed -The EOF is located in the Buchanan Office Building and receives power DG. from two 12 kilovolt (kV) power lines. If one 12 kV line is lost, an automatic transfer switch will shift to the other line. If both lines are lost, an existing 400kW DG will automatically start and supply emergency power. Two uninterruptable power supply (UPS) systems would provide power for a short duration for certain EOF communication equipment and the Local Area Network (LAN) servers if the generator was briefly unavailable.
- 2. The Operations Support Center (OSC). Not Needed -The OSC has not been shown to be survivable for all BDBEEs assessed for CNP. The OSC function may be re-located based on habitability concerns.
The procedure for activation and operation of the OSC designates the Enclosure 2 to AEP-NRC-2014-91 Page 4 Communications Assessment Implementation Timeline Recommendation Stated in I&M Letter dated October 31, 2012 Updated Status~1-Radiation Protection Access Control Building or other onsite location as an alternate location for the OSC as directed by the Radiation Protection Director and the OSC Manager. Personnel manning the primary or alternate onsite OSC can utilize the FLEX radio system and satellite phones. As noted in the letter from J. P. Gebbie, I&M, to NRC, dated May 23, 2014, transmitting the CNP On-Shift Staffing Assessment Report, if access to designated emergency response facilities is not possible, OSC personnel may also respond to the EOF. Power supplies for the EOF are discussed in the updated status items preceding and following this item.Therefore, an alternate power supply to the OSC is not needed to support the FLEX strategies.
Provide standalone UPS units for Complete as Stated -A UPS system feeds the 120V AC distribution panels to support equipment in the EOF and TSC that will be the essential TSC loads, (e.g. computers, multi-line telephones, etc.). The UPS needed to manage the emergency.
system consists of a battery, two battery chargers, two inverters, and two 120V AC (computers, multi-line telephones, and distribution panels.portable phones). As noted above, there are 12 kV power lines and a DG providing redundant power supplies to the EOF. Additionally, two UPS systems would provide power for certain EOF communication equipment and LAN servers. As also noted above, satellite phones (battery powered) would also be available in the EOF. These provision are considered to provide adequate assurance of EOF communication capabilities.
Provide a dedicated source of backup Complete as Stated -Per 1-OHP-4027-FSG-501, "FLEX Equipment Staging," a 26 kW power (portable generator) for charging DG is available in the Turbine Building.
This generator can be used to power portable batteries for handheld radios. charging stations for the radios. Additionally, portable charging stations are available in the FLEX Storage Building and may be staged near any available power source inside or outside the building.
Power can be provided to the FLEX Storage Building by portable generators.
Enclosure 2 to AEP-NRC-2014-91 Page 5 Communications Assessment Implementation Timeline Recommendation Stated in I&M Letter Updated Status dated October 31, 2012 Update training programs to address Complete as Stated -A formal hands-on study guide (FX-I-004, "FLEX Portable emergency communications equipment Communications")
utilizing actual communication equipment and knowledge consistent with implementation of FLEX. demonstrations for the new FLEX communication equipment was developed, and was administered to applicable Operations and Fire Protection personnel.