Similar Documents at Cook |
---|
Category:Letter type:AEP
MONTHYEARAEP-NRC-2024-62, Unit 2 Independent Spent Fuel Storage Installation - Registration of Dry Spent Fuel Storage Cask2024-08-0808 August 2024 Unit 2 Independent Spent Fuel Storage Installation - Registration of Dry Spent Fuel Storage Cask AEP-NRC-2024-47, Form OAR-1, Owners Activity Report2024-07-30030 July 2024 Form OAR-1, Owners Activity Report AEP-NRC-2024-56, Unit 2, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Cask2024-07-0808 July 2024 Unit 2, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Cask AEP-NRC-2024-48, Response to Request for Additional Information (RAI) for License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating2024-07-0202 July 2024 Response to Request for Additional Information (RAI) for License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating AEP-NRC-2024-45, Report Per Technical Specification 5.6.6 for Inoperability of Post Accident Monitoring Neutron Flux Monitoring2024-06-13013 June 2024 Report Per Technical Specification 5.6.6 for Inoperability of Post Accident Monitoring Neutron Flux Monitoring AEP-NRC-2024-23, Core Operating Limits Report2024-05-23023 May 2024 Core Operating Limits Report AEP-NRC-2024-40, Unit 2 - Supplement to License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating2024-05-16016 May 2024 Unit 2 - Supplement to License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating AEP-NRC-2024-41, Annual Radiological Environmental Operating Report2024-05-15015 May 2024 Annual Radiological Environmental Operating Report AEP-NRC-2024-26, Transmittal of Donald C. Cook Nuclear Plant, Emergency Plan Revision 492024-05-14014 May 2024 Transmittal of Donald C. Cook Nuclear Plant, Emergency Plan Revision 49 AEP-NRC-2024-07, Unit 2 - Transmittal of Report of Changes to the Emergency Plan2024-05-14014 May 2024 Unit 2 - Transmittal of Report of Changes to the Emergency Plan AEP-NRC-2024-24, Form OAR-1, Owners Activity Report2024-05-0707 May 2024 Form OAR-1, Owners Activity Report AEP-NRC-2024-35, Response to NRC Regulatory Issue Summary 2024-01 Preparation and Scheduling of Operator Licensing Examinations2024-04-30030 April 2024 Response to NRC Regulatory Issue Summary 2024-01 Preparation and Scheduling of Operator Licensing Examinations AEP-NRC-2024-28, 2023 Annual Radioactive Effluent Release Report2024-04-29029 April 2024 2023 Annual Radioactive Effluent Release Report AEP-NRC-2024-31, Annual Report of Individual Monitoring2024-04-24024 April 2024 Annual Report of Individual Monitoring AEP-NRC-2024-29, (CNP) Unit 2 - Request for Relief Related to American Society of Mechanical Engineers (ASME) Code Case N-729-6 Supplemental Examination Requirements, ISIR-5-072024-04-0303 April 2024 (CNP) Unit 2 - Request for Relief Related to American Society of Mechanical Engineers (ASME) Code Case N-729-6 Supplemental Examination Requirements, ISIR-5-07 AEP-NRC-2024-02, Unit 2 License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating2024-04-0303 April 2024 Unit 2 License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating AEP-NRC-2024-19, Annual Report of Property Insurance2024-04-0101 April 2024 Annual Report of Property Insurance AEP-NRC-2024-04, License Amendment Request Regarding a Change to Unit 1 Technical Specification 3.4.12, Low Temperature Overpressure Protection (LTOP) System2024-03-0606 March 2024 License Amendment Request Regarding a Change to Unit 1 Technical Specification 3.4.12, Low Temperature Overpressure Protection (LTOP) System AEP-NRC-2024-11, Unit 2 - Response to Request for Additional Information on Requested Change Regarding Neutron Flux Instrumentation2024-02-27027 February 2024 Unit 2 - Response to Request for Additional Information on Requested Change Regarding Neutron Flux Instrumentation AEP-NRC-2024-10, Form OAR-1, Owners Activity Report2024-02-0707 February 2024 Form OAR-1, Owners Activity Report AEP-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 2024-08-08
[Table view] |
Text
INDIANA Indiana Michigan Power MICHIGAN Cook Nuclear Plant POWMER One Cook Place Bridgman, MI 49106 A unit of American Electric Power Indiana Mic higanPower.com June 28, 2013 AEP-NRC-2013-59 10 CFR 50.4 Docket Nos. 50-315 50-316 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Donald C. Cook Nuclear Plant Units 1 and 2 Response to Request for Additional Information Regarding Commitment for Implementation of Multi-Unit/Multi-Source Dose Capability
References:
- 1. U.S. Nuclear Regulatory Commission (NRC) Fukushima Near-Term Task Force Report, "Recommendations for Enhancing Reactor Safety in the 2 1 st Century: the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident", dated July 12, 2011, (ADAMS Accession No. ML112510271).
- 2. Letter from Joseph E. Pollock, Nuclear Energy Institute (NEI), to James T. Wiggins, Director of the NRC Office of Nuclear Security Incident and Response, "Industry Implementation of Multi-unit Dose Capability", dated January 28, 2013, (ADAMS Accession No. ML13028A200).
- 3. Letter from James T. Wiggins, NRC, to Joseph E. Pollock, NEI, requesting additional information on licensees' multi-unit dose capability, dated February 27, 2013, (ADAMS Accession No. ML13029A632).
- 4. Letter from Joseph E. Pollock, NEI, to James T. Wiggins, NRC, "Commitment for Implementation of Multi-Unit Dose Capability", dated March 14, 2013, (ADAMS Accession No. ML13073A522).
This letter provides Indiana Michigan Power Company's (I&M), licensee for Donald C. Cook Nuclear Plant (CNP) Units 1 and 2, response to the Request for Additional Information (RAI) from the NRC regarding the current and anticipated capability of I&M to perform multi-unit/multi-source dose assessment in connection with radiological release events at CNP.
In Reference 1, the NRC's Near-Term Task Force highlighted a gap in the capability of United States commercial nuclear power plant licensees to perform multi-unit/multi-source dose assessments. In Reference 2, NEI reported to the NRC the results of a survey of licensees' current ability to perform multi-unit/multi-source dose assessments, those licensees' anticipated time Aoo(
U. S. Nuclear Regulatory Commission AEP-NRC-2013-59 Page 2 frames for obtaining multi-unit/multi-source dose assessment capability, and the compensatory measures to be employed by licensees in the interim period before obtaining multi-unit/multi-source dose assessment capability. In Reference 3, the NRC requested more detailed information regarding the current and anticipated capabilities of licensees to perform multi-unit/multi-source dose assessments. In Reference 4, NEI informed the NRC that the licensees would provide the NRC with the information requested in Reference 2.
In accordance with Reference 4, I&M hereby provides the following information regarding the ability to perform offsite dose assessment during an event involving radiological releases from multiple units or sources at CNP:
RAI I Summarize I&M's current capability to perform multi-unit/multi-source dose assessment during an event involving releases from multiple units or sources at CNP.
I&M RESPONSE TO RAI I I&M's existing software for assessing the radiological impact of accidents at CNP does not have integrated, simultaneous multi-unit/multi-source dose assessment capability. Currently, I&M uses a PC-based software program, Meteorological Information Dose Assessment Software (MIDAS) from ABS Consulting, Inc., for dose assessment in connection with radiological release events at CNP.
MIDAS calculates total effective dose equivalent and thyroid doses at any affected location within 50 miles of CNP. MIDAS derives source term information from CNP effluent monitors, reactor coolant system or containment samples, field monitoring teams, or a default design basis accident scenario.
The version of MIDAS currently in use at CNP can; however, be used to perform dose calculations for individual accidents at CNP; summing those individual dose calculations can approximate the dose received from radiological release events involving multiple units or sources. Further, the version of MIDAS in use at CNP has the capability to perform dose projections from multiple release points at a single unit. MIDAS can also perform dose projections by calculating dispersion of the released radiological material as it travels downwind and estimating the resulting concentrations of that material using event trees based on NUREG-1228, "Source Estimation During Incident Response to Severe Nuclear Power Plant Accidents", and NRC Response Technical Manual (RTM) 96.
RAI 2
Describe I&M's anticipatedschedule to establish multi-unit/multi-source dose assessment capability on an interim or permanent basis, providing due dates for key actions or milestones.
I&M RESPONSE TO RAI 2 I&M has purchased from ABS Consulting Inc., a newly-available upgrade (MIDAS-NU version:
1.5.16.022113) to CNP's existing MIDAS software that will provide integrated multi-unit/multi-source dose assessment capability. This MIDAS software upgrade will provide simultaneous dose
U. S. Nuclear Regulatory Commission AEP-NRC-2013-59 Page 3 assessment capability for radiological release events involving multiple units at CNP, or up to five individual radiological releases at different locations (such as spent fuel pools and dry cask storage locations) at CNP.
I&M has developed the following projected time line for ensuring full implementation of simultaneous multi-unit/multi-source dose assessment capability at CNP by December 31, 2014:
Review Emergency Response procedures for potential changes due to the new 09/01/2013 MIDAS software.
Develop testing criteria and complete acceptance testing for the new MIDAS 10/01/2013 software.
Develop training material for the Emergency Response Organization (ERO) team 10/01/2013 members on the new MIDAS software.
Perform 50.54q Review for transition to the new MIDAS software. 11/01/2013 Complete familiarization training for MIDAS users in the Emergency Operations 12/31/2013 Facility (EOF) and Technical Support Center (TSC) on the new MIDAS software.
Complete familiarization training on the new MIDAS software to Emergency 12/31/2013 Response team members that fill oversight positions.
Complete familiarization training on the new MIDAS software for MIDAS users in the 04/30/2014 Control Rooms.
Complete training of all MIDAS users on the new MIDAS software. 05/31/2014 Install MIDAS-NU version 1.5.16 on all dose assessment computers. 05/31/2014 Please note that the dates within the projected timeline above are not intended to serve as hard deadlines or firm commitments for completion of the corresponding milestones; rather, they are intended to demonstrate I&M's compliance with the NRC's requirement of full implementation of multi-unit/multi-source dose assessment capability by December 31, 2014.
RAI 3
Describe how the multi-unit/multi-source dose assessment capability implementation schedule described above will be tracked by I&M.
I&M RESPONSE TO RAI 3 The milestones and dates within the projected timeline above have been entered into I&M's Action Tracking ActionWay Program and will be tracked under GT 2013-8929.
U. S. Nuclear Regulatory Commission AEP-NRC-2013-59 Page 4 This letter contains no new or revised commitments. If you have any questions, please contact Mr. Michael K. Scarpello at (269) 466-2649.
Sincerely, Joel P. Gebbie Site Vice President JEN/db c: C. A. Casto, NRC Region III J.T. King, MPSC S.M. Krawec, AEP Ft. Wayne MDEQ-RMD/RPS NRC Resident Inspector S. Perkins-Grew, Nuclear Energy Institute T. J. Wengert, NRC Washington, DC