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] Category:Response to Request for Additional Information (RAI)
MONTHYEARML24197A1262024-07-15015 July 2024 Unit 2 - Request for Additional Information (RAI) for License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating 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-2024-11, 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-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-2021-43, Response to Request for Additional Information Regarding Relief Request for Limited Coverage Examinations Performed in the Fourth 10-Year Inspection Interval2021-07-21021 July 2021 Response to Request for Additional Information Regarding Relief Request for Limited Coverage Examinations Performed in the Fourth 10-Year Inspection Interval AEP-NRC-2021-16, Unit 2 - Response to Request for Additional Information Regarding CFR 50.55a Request Associated with the Fifth Ten-Year Inservice Testing Interval2021-02-25025 February 2021 Unit 2 - Response to Request for Additional Information Regarding CFR 50.55a Request Associated with the Fifth Ten-Year Inservice Testing Interval AEP-NRC-2021-18, Response to Request for Additional Information Regarding License Amendment Request for One-Time Extension of the Containment Type a Leak Rate Testing Frequency2021-02-18018 February 2021 Response to Request for Additional Information Regarding License Amendment Request for One-Time Extension of the Containment Type a Leak Rate Testing Frequency AEP-NRC-2020-50, Response to Request for Additional Information Regarding License Amendment Request for One-Time Extension of the Containment Type a Leak Rate Testing Frequency2020-07-0909 July 2020 Response to Request for Additional Information Regarding License Amendment Request for One-Time Extension of the Containment Type a Leak Rate Testing Frequency AEP-NRC-2019-56, Seismic Probabilistic Risk Assessment in Response to Near Term Task Force Recommendation 2.1: Seismic2019-11-0404 November 2019 Seismic Probabilistic Risk Assessment in Response to Near Term Task Force Recommendation 2.1: Seismic AEP-NRC-2019-32, Unit 2 - Response to Request for Additional Information Regarding Unit 2 Leak-Before-Break Analysis and Deletion of Containment Humidity Monitors for Unit 1 and Unit 22019-08-22022 August 2019 Unit 2 - Response to Request for Additional Information Regarding Unit 2 Leak-Before-Break Analysis and Deletion of Containment Humidity Monitors for Unit 1 and Unit 2 AEP-NRC-2019-40, Response to Request for Additional Information Regarding License Amendment Request to Address NSAL-15-1, Rev. 02019-07-30030 July 2019 Response to Request for Additional Information Regarding License Amendment Request to Address NSAL-15-1, Rev. 0 AEP-NRC-2018-81, Supplement to Response to Request for Additional Information Regarding License Amendment Request for Approval of Application of Proprietary Leak-Before-Break Methodology for Reactor Coolant System Small Diameter Piping2018-11-27027 November 2018 Supplement to Response to Request for Additional Information Regarding License Amendment Request for Approval of Application of Proprietary Leak-Before-Break Methodology for Reactor Coolant System Small Diameter Piping AEP-NRC-2018-82, Response to Request for Additional Information Regarding the Alternative Request for Elimination of the Reactor Pressure Vessel Threads in Flange Examination2018-11-20020 November 2018 Response to Request for Additional Information Regarding the Alternative Request for Elimination of the Reactor Pressure Vessel Threads in Flange Examination AEP-NRC-2018-64, Response to Request for Additional Information Regarding License Amendment Request for Approval of Application of Proprietary Leak-Before-Break Methodology for Reactor Coolant System Small Diameter Piping2018-09-27027 September 2018 Response to Request for Additional Information Regarding License Amendment Request for Approval of Application of Proprietary Leak-Before-Break Methodology for Reactor Coolant System Small Diameter Piping ML18334A2722018-09-18018 September 2018 LTR-SDA-II-18-41-NP, Revision 1, Responses to NRC Questions on the Expanded Scope Leak-Before-Break Evaluations for D.C. Cook, Units 1 and 2. AEP-NRC-2018-45, Response to Request for Additional Information Concerning 2017 Decommissioning Funding Status Report2018-08-0909 August 2018 Response to Request for Additional Information Concerning 2017 Decommissioning Funding Status Report AEP-NRC-2018-01, Response to Request for Additional Information Regarding Generic Letter 2016-012018-05-25025 May 2018 Response to Request for Additional Information Regarding Generic Letter 2016-01 AEP-NRC-2018-23, Response to Request for Additional Information Regarding Independent Spent Fuel Storage Installation Decommissioning Funding Plan2018-04-11011 April 2018 Response to Request for Additional Information Regarding Independent Spent Fuel Storage Installation Decommissioning Funding Plan ML18092A0842018-03-28028 March 2018 Donald C. Cook Nuclear Plant Unit 2, Response to Request for Additional Information Regarding Supplemental Information Regarding the Reactor Vessel Internals Aging Management Program ML17346A7662017-12-0808 December 2017 Enclosures 2 & 3 to AEP-NRC-2017-56 - Response to Request for Additional Information Regarding the License Amendment Request to Revise Emergency Action Levels and EAL Technical Basis Manual AEP-NRC-2017-56, Response to Request for Additional Information Regarding the License Amendment Request to Revise Emergency Action Levels2017-12-0808 December 2017 Response to Request for Additional Information Regarding the License Amendment Request to Revise Emergency Action Levels AEP-NRC-2017-30, Response to Request for Additional Information Regarding the License Amendment Request to Revise Technical Specification 3.9.3, Containment Penetrations2017-05-26026 May 2017 Response to Request for Additional Information Regarding the License Amendment Request to Revise Technical Specification 3.9.3, Containment Penetrations AEP-NRC-2017-16, Submittal of Focused Evaluation in Response to March 12, 2012, Request for Information Regarding Near- Term Task Force Recommendation 2.1: Flooding2017-05-11011 May 2017 Submittal of Focused Evaluation in Response to March 12, 2012, Request for Information Regarding Near- Term Task Force Recommendation 2.1: Flooding AEP-NRC-2017-09, Response to Request for Additional Information Regarding the License Amendment Request for the Containment Leakage Rate Testing Program2017-02-27027 February 2017 Response to Request for Additional Information Regarding the License Amendment Request for the Containment Leakage Rate Testing Program AEP-NRC-2016-81, Unit 2 - Supplemental Response to Request for Additional Information Regarding the License Amendment Request to Adopt TSTP-425, Relocate Surveillance Frequencies Program to Licensee Control-Risk Informed ...2016-11-0303 November 2016 Unit 2 - Supplemental Response to Request for Additional Information Regarding the License Amendment Request to Adopt TSTP-425, Relocate Surveillance Frequencies Program to Licensee Control-Risk Informed ... AEP-NRC-2016-80, Response to NRC Generic Letter 2016-01: Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools2016-10-31031 October 2016 Response to NRC Generic Letter 2016-01: Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools AEP-NRC-2016-79, Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident2016-10-12012 October 2016 Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident AEP-NRC-2016-69, Follow-up Response to Request for Additional Information Regarding License Amendment Request to Adopt TSTF-425, Relocate Surveillance Frequencies Program to License Control-Risk Informed Technical Specification Task Force.2016-09-0909 September 2016 Follow-up Response to Request for Additional Information Regarding License Amendment Request to Adopt TSTF-425, Relocate Surveillance Frequencies Program to License Control-Risk Informed Technical Specification Task Force. AEP-NRC-2016-56, Response to Seventh Request for Additional Information Regarding the License Amendment Request to Adopt TSTF-490 and Implement Alternative Source Term2016-07-12012 July 2016 Response to Seventh Request for Additional Information Regarding the License Amendment Request to Adopt TSTF-490 and Implement Alternative Source Term AEP-NRC-2016-54, Response to Request for Additional Information Regarding the License Amendment Request to Adopt TSTF-425, Relocate Surveillance Frequencies to Licensee Control - Risk Informed Technical Specification Task Force Initiative 582016-06-16016 June 2016 Response to Request for Additional Information Regarding the License Amendment Request to Adopt TSTF-425, Relocate Surveillance Frequencies to Licensee Control - Risk Informed Technical Specification Task Force Initiative 58 AEP-NRC-2016-48, Unit 2 - Response to Request for Additional Information Regarding the License Amendment Request to Adopt TSTF-425, Relocate Surveillance Frequencies Program to Licensee-Control...2016-06-16016 June 2016 Unit 2 - Response to Request for Additional Information Regarding the License Amendment Request to Adopt TSTF-425, Relocate Surveillance Frequencies Program to Licensee-Control... ML16169A1152016-05-0606 May 2016 Donald C. Cook Nuclear Plant Units 1 and 2 - Response to Sixth Request for Additional Information the License Amendment Request to Adopt TSTF-490 and Implement Alternative Source Term AEP-NRC-2016-24, Response to Fifth Request for Additional Information Regarding the License Amendment Request to Adopt TSTF-490 and Implement Alternative Source Term2016-02-19019 February 2016 Response to Fifth Request for Additional Information Regarding the License Amendment Request to Adopt TSTF-490 and Implement Alternative Source Term AEP-NRC-2016-14, Response to Request for Additional Information Regarding the License Amendment Request to Revise Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation2016-01-21021 January 2016 Response to Request for Additional Information Regarding the License Amendment Request to Revise Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation AEP-NRC-2015-11, Response (Part 2) to Fourth Request for Additional Information Regarding the License Amendment Request to Adopt TSTF-490 and Implement Alternative Source Term2015-12-17017 December 2015 Response (Part 2) to Fourth Request for Additional Information Regarding the License Amendment Request to Adopt TSTF-490 and Implement Alternative Source Term ML15323A4332015-11-16016 November 2015 Supplemental Response to Request for Additional Information on the Application for Amendment to Restore Normal Reactor Coolant System Pressure and Temperature Consistent with Previously Licensed Conditions. ML15323A4342015-11-16016 November 2015 Response (Part 1) to Fourth Request for Additional Information Regarding the License Amendment Request to Adopt TSTF-490 and Implement Alternative Source Term AEP-NRC-2015-98, Supplemental Response to Follow-Up Request for Additional Information Concerning the Reactor Vessel Internals Aging Management Program2015-10-30030 October 2015 Supplemental Response to Follow-Up Request for Additional Information Concerning the Reactor Vessel Internals Aging Management Program AEP-NRC-2015-99, Response to Request for Additional Information Re License Amendment Request to Revise Technical Specification Section 3.8.1, AC Sources - Operating, Surveillance Requirements 3.8.1.10, 3.8.1.11 and 3.8.1.152015-10-30030 October 2015 Response to Request for Additional Information Re License Amendment Request to Revise Technical Specification Section 3.8.1, AC Sources - Operating, Surveillance Requirements 3.8.1.10, 3.8.1.11 and 3.8.1.15 ML15308A0932015-10-15015 October 2015 Pressurized Water Reactor Owners Group (Pwrog), 15066-NP, Revision 1, Responses to Follow-Up NRC RAI 2 on the D.C. Cook, Units 1 and 2, Reactor Internals Aging Management Program. AEP-NRC-2015-86, Supplemental Response to Request for Additional Information on the Application for Amendment to Restore Normal Reactor Coolant System Pressure and Temperature Consistent With. Previously Licensed Conditions.2015-09-18018 September 2015 Supplemental Response to Request for Additional Information on the Application for Amendment to Restore Normal Reactor Coolant System Pressure and Temperature Consistent With. Previously Licensed Conditions. AEP-NRC-2015-80, Response to Third Request for Additional Information Regarding the License Amendment Request to Adopt TSTF-490 and Implement Alternative Source Term2015-08-28028 August 2015 Response to Third Request for Additional Information Regarding the License Amendment Request to Adopt TSTF-490 and Implement Alternative Source Term AEP-NRC-2015-88, Response to Request for Additional Information Regarding Proposed Alternative to the American Society of Mechanical Engineers Code, Section XI Repair Requirements2015-08-24024 August 2015 Response to Request for Additional Information Regarding Proposed Alternative to the American Society of Mechanical Engineers Code, Section XI Repair Requirements AEP-NRC-2015-75, Response to Second Request for Additional Information Regarding the License Amendment Request to Adopt TSTF-490 and Implement Alternative Source Term2015-08-24024 August 2015 Response to Second Request for Additional Information Regarding the License Amendment Request to Adopt TSTF-490 and Implement Alternative Source Term AEP-NRC-2015-69, Response to Follow-Up Request for Additional Information Concerning the Reactor Vessel Internals Aging Management Program2015-08-0606 August 2015 Response to Follow-Up Request for Additional Information Concerning the Reactor Vessel Internals Aging Management Program ML15223A4362015-07-28028 July 2015 PWROG-15066-NP, Revision 0, Responses to Follow-Up NRC RAI 2 on the DC Cook Units 1 and 2 Reactor Internals Aging Management Program. AEP-NRC-2015-63, Response to Request for Additional Information Regarding 2014 Unit 1 Steam Generator Tube Inspection2015-07-17017 July 2015 Response to Request for Additional Information Regarding 2014 Unit 1 Steam Generator Tube Inspection AEP-NRC-2015-64, Response to Request for Additional Information Regarding the License Amendment Request to Adopt TSTF-490 and Implement Alternative Source Term2015-07-17017 July 2015 Response to Request for Additional Information Regarding the License Amendment Request to Adopt TSTF-490 and Implement Alternative Source Term AEP-NRC-2015-60, Response to a Request for Additional Information Regarding the License Amendment Request to Revise Technical Specification Section 3.8.1, AC Sources - Operating, Surveillance Requirements 3.8.1.10, 3.8.1.11, and 3.8.1.152015-07-0909 July 2015 Response to a Request for Additional Information Regarding the License Amendment Request to Revise Technical Specification Section 3.8.1, AC Sources - Operating, Surveillance Requirements 3.8.1.10, 3.8.1.11, and 3.8.1.15 2024-07-02
[Table view] |
Text
INDIANA MICHIGAN Indiana Michigan Power Cook Nuclear Plant POWER
- One Cook Place Bridgrnan, MI 49106 A unitafAmerican ElectricPower India na Michig anPower. corn October 30, 2015 AEP-NRC-201 5-98 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 SUPPLEMENTAL RESPONSE TO FOLLOW-UP REQUEST FOR ADDITIONAL INFORMATION CONCERNING THE REACTOR VESSEL INTERNALS AGING MANAGEMENT PROGRAM
References:
- 1) Letter from J. P. Gebbie, Indiana Michigan Power Company (I&M), to U. S. Nuclear Regulatory Commission (NRC), "Donald C. Cook Nuclear Plant Units 1 and 2, Transmittal of Reactor Vessel Internals Aging Management Program," dated October 1, 2012, Agencywide Documents Access and Management System (ADAMS) Accession No. ML12284A320.
Wengert, NRC, to L. J. Wieber, I&M, "Donald C. Cook Nuclear Plant, Units and T.2 J.
- 2) Letter Ifrom - Request for Additional Information Concerning the Reactor Vessel Internals Aging Management Program Submittal (TAC Nos. MF0050 and MF0051),"
dated June 6, 2014, ADAMS Accession No. ML14135A320.
- 3) Letter from J. P. Gebbie, I&M, to NRC, "Donald C. Cook Nuclear Plant Units I and 2
- First Response to Request for Additional Information Concerning the Reactor Vessel Internals Aging Management Program," dated July 30, 2014, ADAMS Accession No. ML14216A497.
- 4) Letter from J. P. Gebbie, I&M, to NRC, "Donald C. Cook Nuclear Plant Units I and 2
- Second Response to Request for Additional Information Concerning the Reactor Vessel Internals Aging Management Program," dated September 4, 2014, ADAMS Accession No. ML14253A316.
- 5) Letter from J. P. Gebbie, I&M, to NRC, "Donald C. Cook Nuclear Plant Units 1 and 2
- Final Response to Request for Additional Information Concerning the Reactor Vessel Internals Aging Management Program," dated October 22, 2014, ADAMS Accession No. ML14316A449.
$loD(
U.S. Nuclear Regulatory Commission AEP-NRC-201 5-98 Page 2
- 6) Letter from A. W. Dietrich, NRC, to L. J. Weber, I&M, "Donald C. Cook Nuclear Plant, Units 1 and 2 - Follow-Up Request for Additional Information Concerning the Reactor Vessel Internals Aging Management Program Submittal (TAC Nos. MF0050 and MF0051)," dated May 5, 2015, ADAMS Accession No. ML15119A339.
- 7) Letter from J. P. Gebbie, I&M, to NRC, "Donald C. Cook Nuclear Plant Units 1 and 2
- Response to Follow-up Request for Additional Information concerning the Reactor Vessel Internals Aging Management Program," dated August 6, 2015, ADAMS Accession Nos. ML15223A435 and ML15233A436.
- 8) Letter from A. W. Dietrich, NRC, to I&M, "Summary of September 23, 2015, Public Meeting with Indiana Michigan Power Company Regarding Donald C. Cook Nuclear Plant, Units 1 and 2 (TAC NOS. MF0050 and MF0051)," dated October 5, 2015, ADAMS Accession No. ML15271A046.
This letter provides Indiana Michigan Power Company's (I&M), licensee for Donald C. Cook Nuclear Plant (CNP) Units 1 and 2, supplemental response to the follow-up request for additional information (RAI) by the U. S. Nuclear Regulatory Commission (NRC) regarding CNP's Reactor Vessel Internals (RVI) Aging Management Program (AMP).
By Reference 1, I&M submitted the CNP RVI AMP. By References 2 and 6, the NRC transmitted RAIs regarding the program. References 3, 4, 5, and 7 provided l&M's responses to References 2 and 6. By Reference 8, the NRC requested clarification of the follow-up RAI response for RAI-2(b) of Reference 6. to this letter provides a response to Reference 8. Enclosure 2 provides PWROG-1 5066-NP, Revision 1, "Responses to Follow-Up NRC RAI 2 on the DC Cook Units 1 and 2 Reactor Internals Aging Management Program," dated October 15, 2015.
There are no new commitments in this letter. 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/ams
Enclosures:
- 1. Supplemental Response to Follow-Up Request for Additional Information Regarding the Reactor Vessel Internals Aging Management Program
- 2. PWROG-15066-NP, Revision 1, Responses to Follow-Up NRC RAI 2 on the DC Cook Units 1 and 2 Reactor Internals Aging Management Program
U.S. Nuclear Regulatory Commission AEP-NRC-201 5-98 Page 3 c: A. W. Dietrich, NRC Washington, D.C.
J. T. King - MPSC MDEQ- RMD/RPS NRC Resident Inspector C. D. Pederson, NRC Region III A. J. Williamson - AEP Ft. Wayne, wlo enclosures
ENCLOSURE 1 TO AEP-NRC-201 5-98 SUPPLEMENTAL RESPONSE TO FOLLOW-UP REQUEST FOR ADDITIONAL INFORMATION REGARDING THE REACTOR VESSEL INTERNALS AGING MANAGEMENT PROGRAM List of Acronyms and Abbreviations:
-A NRC Approved (by Safety Evaluation)
ADAMS Agencywide Documents Access and Management System AMP Aging Management Program ASME American Society of Mechanical Engineers CASS Cast Austenitic Stainless Steel CMTR. Certified Material Test Report CNP Donald C. Cook Nuclear Power Plant CRGT Control Rod Guide Tube EPRI Electric Power Research Institute I&M Indiana Michigan Power Company kJim2 Kilojoule per Meter Squared MRP EPRI Materials Reliability Program .
MSC PWROG Materials Committee (legacy Materials Subcommittee)
NEI Nuclear Energy Institute
-NP Non-Proprietary NRC U. S. Nuclear Regulatory Commission
-P Proprietary PA- PWROG Project Authorization PWR Pressurized Water Reactor PWROG Pressurized Water Reactor Owners Group RAl Request for Additional Information RCCA Rod Control Cluster Assembly RVI Reactor Vessel Internals SR Surveillance Requirement TS Technical Specification VT Visual Testing WAAP Westinghouse Association Activities Paper WCAP Westinghouse Commercial Atomic Power Introduction By letter datedOctober 1, 2012 (ADAMS Accession No. ML12284A320), I&M, the licensee for CNP, submitted an AMP for CNP, Units 1 and 2, RVI to the NRC. By letter dated June 6, 2014 (ADAMS Accession No. ML14135A320), the NRC staff reviewed the submittal and requested additional information to ,complete its review. By letter dated, July 30, 2014 (ADAMS Accession No. ML14216A497), the responses to RAI-1, RAI-5, and RAI-7 were provided to the NRC. By letter dated September 4, 2014 (ADAMS Accession Nos. ML14253A316, ML14253A317, and ML14253A318), the response to RAI-8 was provided to the NRC. By letter dated October 22, 2014 (ADAMS Accession No. ML14316A449), the responses to RAI-2, RAI-3, RAI-4, and RAI-6 were provided to the NRC. By letter dated May 5, 2015 (ADAMS Accession No. ML15119A339), the NRC staff transmitted a follow-up RAl to complete its review. By letter dated August 6, 2015
Enclosure 1Ito AEP-NRC-2015-98 Pg Page 2 (ADAMS Accession Nos. ML15223A435 & ML15223A436), a response to the follow-up RAI was provided. By letter dated September 11, 2015 (ADAMS Accession No. ML15257A289), the NRC scheduled a public teleconference where the staff requested clarification and a supplemental submittal for four specific items in the response to follow-up RAl provided by I&M. By meeting summary dated October 5, 2015 (ADAMS Accession No. ML15271A046), the NRC documented the request for elaboration on the four statements made in I&M's response to follow-up RAI-2(b),
Clarification of these four items from the response to the follow-up RAl is provided in this enclosure with additional information provided in Enclosure 2.
Requested Clarification A detailed response to follow-up RAI-2(b) was provided by letter dated August 6, 2015, "Response to Follow-Up Request for Additional Information Concerning the Reactor Vessel internals Aging Management Program," in Enclosure 2, PWROG-1 5066-NP, Revision 0, "Responses to Follow-Up NRC RAl 2 on the DC Cook Units 1 and 2 Reactor Internals Aging Management Program." The NRC requested that l&M elaborate on four items from the response in this document during a public meeting held on September 23, 2015. These four items are listed below with additional detail following each item.
A detailed records search revealed that the CNP Unit 1 CRGT guide cards were specified with a primary material of wrought Type 304 stainless steel, with an alternate material of CASS CF8 allowed. No CMTR or other manufacturing record was located which indicated the fabrication material. It is expected that the components are fabricated from wrought Type 304 stainless steel.
However, in the absence of confirmatory records, these components are conservatively assumed to be fabricated from CASS CF8.
Item #1 : Requested Clarification from Response to Follow-Up RAI-2(b), CASS CRGT Guide Card Cracking Effects Observations Thermal embrittlementof CASS does not result in a complete loss of fracture toughness. Even with complete thermal embrittlement, a significant amount of fracture toughness would remain in the card.
Additional Detail on Item #1:
A meeting was held between the PWROG and NRC on September 16, 2015, to discuss a statistical approach to evaluating CASS. Presentation WAAP-9551, "PA-MSC-1288R0: PWR Materials Assessment Results," was provided and discussed with the NRC staff. The results of the PWROG work identified that RVI materials fabricated from CF8 material show saturation fracture toughness has a large margin above the 255 kJim2 screening criteria provided in the Grimes Letter (ADAMS Accession No. ML003717179). The minimum fracture toughness of CASS CF8 was 100 kJim2 over the screening criteria.
In lieu of plant specific information on the potentially CASS guide cards in CNP Unit 1, I&M proposes to use the industry-wide distribution discussed above to identify the fracture toughness of these components. The industry-wide distribution has a non-significant reduction in fracture toughness due to thermal embrittlement. Therefore, this set of components is considered to have a to AEP-NRC-201 5-98 Pg Page 3 non-significant reduction in fracture toughness and does not require additional aging management requirements due to thermal embrittlement. to this letter, PWROG-1 5066-NP, Revision 1, 'Responses to Follow-Up NRC RAI 2 on the DC Cook Units 1 and 2 Reactor Internals Aging Management Program," under the section title "Response to Request Part (b)," has been enhanced to provide further discussion and clarification of Item #1.
Item #2: Requested Clarification from Response to Follow-Up RAI-2(b), CASS CRGT Guide Card Conclusion Considerations The scope of the current VT-3 PrimaryComponent inspection for wearrequiredunder MRP-227-A
[3], which would detect gross failures.
Additional Detail to Item #2:
The requirements of VT-3 inspections are provided in ASME Boiler & Pressure Vessel Code,Section XI, with additional details specific to RVI inspections under MRP-227-A provided in MRP-228, Revision 1, "Materials Reliability Program: Inspection Standard for PWR Internals -2012 Update."
In addition to the guidance provided in EPRI report MRP-227-A, "Materials Reliability Program:
Pressurized Water Reactor Internals Inspection and Evaluation Guidelines," as published in December 2011, CNP will also follow the interim guidance provided in EPRI letter MRP 2014-006 (ADAMS Accession No. ML1I4274A372), "MaterialsReliabilityProgram:Pressurized Water Reactor Internals Inspection and Evaluation Guidelines (MRP-227-A), EPRI, Palo Alto, CA: 2011. 1022863, Transmittal of Interim Guidance," published February 2014. This letter provides interim guidance related to MRP-227-A, Table 4-3, "Westinghouse plants Primary Components," and Table 5-3, "Westinghouse plants examination acceptance and expansion criteria." The interim guidance issued by EPRI directs utilities to follow guidance provided in WCAP-1 7451-P (ADAMS Accession No. ML15041A106), Revision 1, "Reactor Internals Guide Tube Wear- Westinghouse Domestic Fleet Operational Projections." I&M is following the six NEI 03-08 "needed" requirements described in Section 6, "Summary Conclusions and Actions."
I&M plans to inspect, at a minimum, all active rodded CRGTs as recommended in WCAP-1 7451 -P, Section 5.5.2, "Extent of Wear Inspections or Measurements," which exceeds the existing requirements of "20% of the number of CRGT assemblies, with all guide cards within each selected CRGT assembly examined," from MRP-227-A. The actual inspection coverage may vary depending upon accessibility and field conditions.
This inspection strategy is adequate to detect cracking prior to loss of function of the guide cards.
While the inspection will be primarily used to evaluate wear, it will also detect damage such as deformed guide card sections and missing card ligaments. The VT-3 inspection is not intended to detect fine cracking. However, the components remain functional until cracking becomes extensive enough that it is detectable by VT-3 inspection.
Therefore, the existing inspection strategy is adequate and does not require additional aging management requirements.
Enclosure 1ito AEP-NRC-2015-98 Pg Page 4 Enclosure 2 to this letter, PWROG-15066-NP, Revision 1, under the section title "Response to Request Part (b)," has been enhanced to provide further discussion and clarification of Item #2.
Item #3: Requested Clarification from Response to Follow-Up RAI-2(b), CASS CRGT Guide Card Conclusion Considerations The redundancyof the component - failures at multiple cards would be requiredfor the control rods to slip out of place and the failure of the control rods in one CRG T assembly to insert would not preclude safe shutdown.
- Additional Detail on Item #3:
A discussion of the redundancy of the CRGT guide cards can be found in WCAP-1 7451-P. CNP Unit 1 is a 4-loop Westinghouse design. Table 4-1, "Plant Groupings," identifies the CNP Unit 1 guide tube design and Figure 2-21, "Guide Tube Design Layouts," describes the CNP Unit 1 general geometry. This information is used in Table 5-10, "Summary of Allowable Number of Worn-Through (Open) Guide Cards," to find the number of allowable consecutive open guide cards. Section 5.2.1, "Guide Card Wear Criteria," provides a discussion and further context of the allowable consecutive open guide cards.
CNP Unit 1 maintains shutdown margin as described in TS, Section 1.1 "Definitions," item "Shutdown Margin," which assumes that all RCCAs are fully inserted, except for the single RCCA of highest reactivity worth, which is assumed to be fully withdrawn (failed to insert). Therefore, in addition to the redundancy of the CRGT guide cards, there is redundancy in the CRGT assemblies with respect to shutdown margin.
Enclosure 2 to this letter, PWROG-15066-NP, Revision 1, under the section title "Response to Request Part (b)," has been enhanced to provide further discussion and Clarification of Item #3.
Item #4: Requested Clarification from Response to Follow-Up RAI-2(b), CASS CRGT Guide Card Conclusion Considerations The periodic monitoring of control rod functionality under current plant procedures.
Additional Detail to Item #4:
Control rod functionality and operability is monitored through testing, which provides evidence of the absence of damage impacting the function of the guide cards:
- 1. Control Rod Dragq Testingq Control rod drag testing is performed every time a RCCA is latched to a drive shaft. RCCAs are latched to their respective drive shaft each time the reactor is reassembled, including following each refueling outage. The drag testing demonstrates that predetermined resistance load acceptance criteria are met.
Enclosure i1to AEP-NRC-2015-98 Page 5
- 2. Control Rod Drop Testingq Control rod drop testing is performed, at a minimum, each time the reactor vessel closure head is removed, prior to reactor criticality, in accordance with TS SR 3.1.4.3. The drop testing demonstrates rod drop times are within predetermined acceptance criteria following maintenance and/or refueling, and prior to reactor criticality.
- 3. Quarterly Operability Surveillance Control rod operability testing is performed quarterly in accordance with TS SR 3.1.4.2. The operability testing moves each rod which is not fully inserted by a minimum number of steps in either direction to validate that behavior is within predetermined acceptance criteria. to this letter, PWROG-15066-NP, Revision 1, under the section title "Response to Request Part (b)," has been enhanced to provide further discussion and clarification of Item #4.