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Category:Letter
MONTHYEARIR 05000315/20230042024-01-31031 January 2024 Integrated Inspection Report 05000315/2023004 and 05000316/2023004 ML24004A1582024-01-19019 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0039 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) 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 ML23352A3502023-12-19019 December 2023 Dc. Cook Nuclear Power Plant, Units 1 Biennial Licensed Operator Requalification Program Inspection and Request for Information ML23338A2642023-12-0505 December 2023 Confirmation of Initial License Examination 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 IR 05000315/20234042023-11-0606 November 2023 Cyber Security Inspection Report 05000315/2023404 and 05000316/2023404 ML23310A1152023-11-0606 November 2023 Notification of the NRC Baseline Inspection and Request for Information, Inspection Report 05000316/2024002 IR 05000315/20234032023-09-19019 September 2023 Security Baseline Inspection Report 05000315/2023403 and 05000316/2023403 IR 05000315/20230112023-08-31031 August 2023 Functional Engineering Inspection - Commercial Grade Dedication Report 05000315/2023011 and 05000316/2023011 ML23242A1832023-08-30030 August 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report05000315/2023004 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 IR 05000315/20234022023-08-11011 August 2023 Security Baseline Inspection Report 05000315/2023402 and 05000316/2023402 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 IR 05000315/20230022023-07-24024 July 2023 Integrated Inspection Report 05000315/2023002 and 05000316/2023002 ML23178A2422023-06-28028 June 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III IR 05000315/20230122023-06-22022 June 2023 Biennial Problem Identification and Resolution Inspection Report 05000315/2023012 and 05000316/2023012 IR 05000315/20235012023-06-21021 June 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000315/2023501 and 05000316/2023501 AEP-NRC-2023-29, Core Operating Limits Report2023-06-19019 June 2023 Core Operating Limits Report ML23159A0192023-06-13013 June 2023 Information Meeting with a Question and Answer Session to Discuss NRC 2022 End-Of-Cycle Plant Performance Assessment of Donald C. Cook Nuclear Plant, Units 1 and 2 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 ML23131A3282023-05-11011 May 2023 D.C. Cook Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000315/2023404 and 05000316/2023404 IR 05000315/20230012023-05-0303 May 2023 Integrated Inspection Report 05000315/2023001 and 05000316/2023001 AEP-NRC-2023-19, Annual Radioactive Effluent Release Report2023-04-30030 April 2023 Annual Radioactive Effluent Release Report ML23117A0062023-04-27027 April 2023 Review of the Spring 2022 Steam Generator Tube Inspections Report ML23114A1142023-04-25025 April 2023 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection 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 ML23076A0212023-03-20020 March 2023 Request for Information for NRC Commercial Grade Dedication Inspection; Inspection Report 05000315/2023011; 05000316/2023011 IR 05000315/20234012023-03-16016 March 2023 Security Baseline Inspection Report 05000315/2023401 and 05000316/2023401 ML23066A1882023-03-0707 March 2023 Information Request to Support Upcoming Problem Identification and Resolution (Pi&R) Inspection at Donald C. Cook Nuclear Plant IR 05000315/20220062023-03-0101 March 2023 Annual Assessment Letter for Donald C. Cook Nuclear Plant, Units 1 and 2 (Report 05000315/2022006 and 05000316/2022006) IR 05000315/20220042023-02-0101 February 2023 Integrated Inspection Report 05000315/2022004 and 05000316/2022004 and Exercise of Enforcement Discretion AEP-NRC-2023-11, Form OAR-1, Owner'S Activity Report2023-01-31031 January 2023 Form OAR-1, Owner'S Activity Report IR 05000315/20230102023-01-31031 January 2023 Phase 4 Post-Approval License Renewal Inspection Report 05000315/2023010 and 05000316/2023010 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 ML22363A5622023-01-0404 January 2023 Relief Request ISIR-5-06 Related to ASME Code Case N-729-6 Supplemental Examination Requirements of Reactor Vessel Closure Head Penetration Nozzles 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 ML22340A1392022-11-30030 November 2022 Submittal of Revision 31 to Updated Final Safety Analysis Report and 10CFR50.71(e) Updated and Related Site Change Reports IR 05000315/20220112022-11-0404 November 2022 Design Basis Assurance Inspection (Teams) Inspection Report 05000315/2022011 and 05000316/2022011 IR 05000315/20220032022-10-28028 October 2022 Integrated Inspection Report 05000315/2022003 and 05000316/2022003 AEP-NRC-2022-58, U1C31 Steam Generator Tube Inspection Report2022-10-24024 October 2022 U1C31 Steam Generator Tube Inspection Report 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 2024-01-08
[Table view] Category:License-Operating (New/Renewal/Amendments) DKT 50
MONTHYEARML22214A0012022-10-0707 October 2022 Issuance of Amendment Nos. 361 and 343 Regarding Adoption of TSTF-554, Revise Reactor Coolant Leakage Requirements ML22046A2332022-06-21021 June 2022 Issuance of Amendment Nos. 360 and 342 Regarding Change to the Technical Specification Requirement for Containment Water Level Instrumentation ML22126A1922022-05-11011 May 2022 Correction to Pages Issued for Amendment No. 359 Regarding Adoption of TSTF-577, Revised Frequencies for Steam Generator Tube Inspections ML22102A0122022-05-0202 May 2022 Issuance of Amendment Nos. 359 and 340 Regarding Adoption of TSTF-577, Revised Frequencies for Steam Generator Tube Inspections ML21062A1882021-03-23023 March 2021 Issuance of Amendment No. 339 One Cycle Extension of Appendix J, Type a, Integrated Leakage Rate Test Interval (EPID L-2020-LLA-0280 (COVID-19)) ML21041A0862021-03-0303 March 2021 Issuance of Amendment No. 338 Regarding One-Time Deferral of the Steam Generator Tube Inspections ML21006A4582021-02-0202 February 2021 Issuance of Amendments Nos. 358 and 337 Regarding Revision to Technical Specifications to Adopt Technical Specifications Task Force Traveler 541, Revision 2 ML20366A1552021-01-15015 January 2021 Issuance of Amendments Nos. 357 and 336 Regarding Revision to Technical Specifications Bases Control Program ML20329A0012021-01-12012 January 2021 Issuance of Amendment No. 356 Regarding Updating the Reactor Coolant System Pressure-Temperature Limits ML20322A4282021-01-0606 January 2021 Issuance of Amendment Nos. 355 and 335, Revision to Technical Specifications to Adopt Technical Specification Task Force Traveler 567, Revision 1, Add Containment Sump TS to Address GSI-191 Issues ML20315A4832020-12-30030 December 2020 Issuance of Amendment Nos. 354 and 334 Adopt Technical Specification Task Force Traveler TSTF-412, Revision 3, Provide Actions for One Steam Supply to the Turbine Driven Afw/Efw Pump Inoperable ML20213C7042020-09-0303 September 2020 Issuance of Amendment No. 353 One Cycle Extension of Appendix J, Type a, Integrated Leakage Rate Test Interval ML19347B3762020-01-31031 January 2020 Issuance of Amendment Nos. 350 and 331, Revise Technical Specification 5.5.5, Reactor Coolant Pump Flywheel Inspection Program, in Accordance with Technical Specification Task Force TSTF-421 ML19329A0112020-01-23023 January 2020 Issuance of Amendment Numbers 349 and 330 to Apply Leak Before-Break Methodology to Reactor Coolant System Branch Lines and Deletion of Containment Humidity Monitor ML19304B6722019-12-31031 December 2019 Issuance of Amendment Numbers 348 and 329 to Revise Operating Licenses DPR-58 and DPR-74, to Address Issues Identified in Westinghouse Document NSAL-15-1 ML19259A0542019-10-15015 October 2019 Issuance of Amendment to Revise Operating Licenses DPR-58 and DPR-74, Appendix B, Environmental Technical Specifications, Part II, Non-Radiological Environment Protection Plan ML19170A3622019-08-0101 August 2019 Issuance of Amendment Approval of Application of Proprietary Leak-Before-Break Methodology for Reactor Coolant System Small Diameter Piping ML19031B9662019-04-10010 April 2019 Issuance of Amendments 344, 326 Regarding Request to Adopt TSTF-529, Revision 4, Clarify Use and Application Rules ML18346A3582019-02-0505 February 2019 Issuance of Amendments 343 and 325 Regarding the Battery Monitoring and Maintenance Program AEP-NRC-2018-66, Request for License Amendment to Technical Specification 3.4.15, RCS Leakage Detection Instrumentation, and Application of Leak-Before-Break Methodology2018-11-20020 November 2018 Request for License Amendment to Technical Specification 3.4.15, RCS Leakage Detection Instrumentation, and Application of Leak-Before-Break Methodology ML18284A2542018-11-16016 November 2018 Issuance of Amendments Request for Deviation from National Fire Protection Association 805 Requirements ML18249A0192018-11-13013 November 2018 Issuance of Amendment Nos. 341 and 323 Technical Support Center Relocation ML18131A2532018-07-0606 July 2018 Issuance of Amendments Request for Deviation from National Fire Protection Association 805 Requirements ML17312B0302017-12-19019 December 2017 Issuance of Amendments License Amendment Request to Revise Technical Specifications Section 3.7.2, Steam Generator Stop Valves (CAC Nos. MF9539 and MF9540; EPID L-2017-LLA-0198) ML17214A5502017-09-21021 September 2017 Issuance of Amendments License Amendment Request Regarding Technical Specification 3.9.3, Containment Penetrations ML17131A2772017-06-0707 June 2017 Issuance of Amendments License Amendment Request Regarding Containment Leakage Rate Testing Program ML17103A1062017-05-24024 May 2017 Issuance of Amendments Adoption of TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing ML17045A1502017-03-31031 March 2017 Issuance of Amendments Adopting of TSTF0425-A, Revision 3, Relocate Surveillance Frequencies to Licensee Control - RITSTF Initiative 5B ML16258A3402016-11-0202 November 2016 Issuance of Amendments Cyber Security Implementation Schedule ML16242A1112016-10-20020 October 2016 DC Cook, Units 1 and 2 - Issuance of Amendments Adoption of TSTF-490,REV.0,Deletion of E-Bar Definition and Revision to Reactor Coolant System Specific Activity Technical Specification and Implementation of Full-Scope Alternative Source Ter ML16216A1812016-08-19019 August 2016 Issuance of Amendment to Revise Technical Specification 3.3.2, Engineered Safety Feature Actuation System Instrumentation ML16195A0042016-08-0404 August 2016 Issuance of Amendments to Revise Technical Specifications to Adopt Technical Specifications Task Force - 523, Generic Letter 2008 01, Managing Gas Accumulation ML15327A2172015-12-11011 December 2015 Issuance of Amendments Technical Specifications Surveillance Requirements 3.8.1.10, 3.8.1.11, and 3.8.1.15 ML14197A0972015-11-30030 November 2015 Issuance of Amendment Regarding Restoration of Normal Reactor Coolant System Pressure and Temperature Consistent with Previously Licensed Conditions ML15187A0022015-07-10010 July 2015 Issuance of Amendment No. 328 (Exigent) Regarding Revision to Technical Specifications for Engineered Safety Feature Actuation System ML15076A2262015-04-0606 April 2015 Issuance of Amendments Adoption of TSTF-427, Allowance for Non-Technical Specification Barrier Degradation on Supported System Operability, Revision 2 ML15072A2642015-03-30030 March 2015 Issuance of Amendments Containment Leakage Rate Testing Program (TACs MF3568 and MF3569) ML14317A5512014-12-18018 December 2014 Issuance of Amendments Cyber Security Implementation Schedule (Tac Nos. MF3363 and MF3364) ML14282A1182014-11-20020 November 2014 Issuance of Amendments Regarding Containment Divider Barrier Seal ML13140A3982013-10-24024 October 2013 Issuance of Amendment Nos. 322 and 305 - Transition to NFPA 805 Risk-Informed, Performance-Based Fire Protection Program in Accordance with 10 CFR 50.48(c) and NFPA 805 ML13282A2142013-10-0909 October 2013 Issuance of Amendment Revision to Technical Specification 3.6.9, Distributed Ignition System (Dis) (Emergency Circumstances) ML12318A2342012-12-13013 December 2012 Issuance of Amendments Revised Cyber Security Plant Implementation Schedule Milestone 6 ML12320A5442012-11-15015 November 2012 DC Cook CDBI Response to Question 2012-CDBI-298 ML12138A3982012-08-23023 August 2012 Issuance of Amendment No. 302 Regarding Optimized Zirlo Clad Fuel Rods ML11251A2272011-11-0303 November 2011 Issuance of Amendment to Relocate Closure Time Requirements for Certain Valves Per TSTF-491 ML11249A0902011-11-0101 November 2011 Issuance of Amendment to Reflect TSTF-513 Regarding Reactor Coolant Leakage Detection Instrumentation ML1116100202011-08-25025 August 2011 Issuance of Amendment No. 316 Use of Optimized Zirlo Fuel Design ML11182A1782011-07-28028 July 2011 License Amendment, Issuance of Amendments Cyber Security Plan ML11112A1232011-06-0101 June 2011 Issuance of Amendment No 314 and 298 to Units 1 and 2 Containment Spray Nozzle Surveillance ML1107307832011-03-31031 March 2011 (CNP-2)-Issuance of Amendment No. 297 Re. Large-Break Loss-of-Coolant Accident Analysis 2022-06-21
[Table view] Category:Safety Evaluation
MONTHYEARML22363A5622023-01-0404 January 2023 Relief Request ISIR-5-06 Related to ASME Code Case N-729-6 Supplemental Examination Requirements of Reactor Vessel Closure Head Penetration Nozzles ML22214A0012022-10-0707 October 2022 Issuance of Amendment Nos. 361 and 343 Regarding Adoption of TSTF-554, Revise Reactor Coolant Leakage Requirements ML22166A3302022-07-26026 July 2022 Review of Quality Assurance Program Changes ML22046A2332022-06-21021 June 2022 Issuance of Amendment Nos. 360 and 342 Regarding Change to the Technical Specification Requirement for Containment Water Level Instrumentation ML22055A0012022-06-0808 June 2022 Issuance of Amendment No. 341 Updating the Reactor Coolant System Pressure Temperature Limits ML22102A0122022-05-0202 May 2022 Issuance of Amendment Nos. 359 and 340 Regarding Adoption of TSTF-577, Revised Frequencies for Steam Generator Tube Inspections ML21295A0092021-11-0303 November 2021 Relief Request ISIR-4-11 Limited Coverage Examinations During the Fourth 10 Year Inservice Inspection Interval ML21141A2612021-06-0202 June 2021 Alternative Request REL-PP2 Related to Fifth 10-Year Inservice Testing Program Interval ML21130A0082021-05-12012 May 2021 Relief Request ISIR-5-05 Related to ASME Code Case N 729-6 Supplemental Examination Requirements of Reactor Vessel Closure Head Penetration Nozzles (EPID L-2021-LLR-0033 (COVID-19)) ML21062A1882021-03-23023 March 2021 Issuance of Amendment No. 339 One Cycle Extension of Appendix J, Type a, Integrated Leakage Rate Test Interval (EPID L-2020-LLA-0280 (COVID-19)) ML21041A0862021-03-0303 March 2021 Issuance of Amendment No. 338 Regarding One-Time Deferral of the Steam Generator Tube Inspections ML21034A1552021-02-12012 February 2021 Relief Request ISIR-5-04 Related to ASME Code Case N-729-6 Supplemental Examination Requirements of Reactor Vessel Closure Head Penetration Nozzles ML21006A4582021-02-0202 February 2021 Issuance of Amendments Nos. 358 and 337 Regarding Revision to Technical Specifications to Adopt Technical Specifications Task Force Traveler 541, Revision 2 ML20366A1552021-01-15015 January 2021 Issuance of Amendments Nos. 357 and 336 Regarding Revision to Technical Specifications Bases Control Program ML20366A1342021-01-13013 January 2021 Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques ML20329A0012021-01-12012 January 2021 Issuance of Amendment No. 356 Regarding Updating the Reactor Coolant System Pressure-Temperature Limits ML20322A4282021-01-0606 January 2021 Issuance of Amendment Nos. 355 and 335, Revision to Technical Specifications to Adopt Technical Specification Task Force Traveler 567, Revision 1, Add Containment Sump TS to Address GSI-191 Issues ML20315A4832020-12-30030 December 2020 Issuance of Amendment Nos. 354 and 334 Adopt Technical Specification Task Force Traveler TSTF-412, Revision 3, Provide Actions for One Steam Supply to the Turbine Driven Afw/Efw Pump Inoperable ML20247J6562020-09-10010 September 2020 Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML20213C7042020-09-0303 September 2020 Issuance of Amendment No. 353 One Cycle Extension of Appendix J, Type a, Integrated Leakage Rate Test Interval ML19347B3762020-01-31031 January 2020 Issuance of Amendment Nos. 350 and 331, Revise Technical Specification 5.5.5, Reactor Coolant Pump Flywheel Inspection Program, in Accordance with Technical Specification Task Force TSTF-421 ML19329A0112020-01-23023 January 2020 Issuance of Amendment Numbers 349 and 330 to Apply Leak Before-Break Methodology to Reactor Coolant System Branch Lines and Deletion of Containment Humidity Monitor ML19304B6722019-12-31031 December 2019 Issuance of Amendment Numbers 348 and 329 to Revise Operating Licenses DPR-58 and DPR-74, to Address Issues Identified in Westinghouse Document NSAL-15-1 ML19259A0542019-10-15015 October 2019 Issuance of Amendment to Revise Operating Licenses DPR-58 and DPR-74, Appendix B, Environmental Technical Specifications, Part II, Non-Radiological Environment Protection Plan ML19196A0642019-08-23023 August 2019 Relied Request ISIR-4-10 Regarding Fourth Inservice Inspection Program Interval ML19170A3622019-08-0101 August 2019 Issuance of Amendment Approval of Application of Proprietary Leak-Before-Break Methodology for Reactor Coolant System Small Diameter Piping ML19134A3552019-07-11011 July 2019 Issuance of Amendments Technical Specification Task Force (TSTF) Traveler 563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program ML19031B9662019-04-10010 April 2019 Issuance of Amendments 344, 326 Regarding Request to Adopt TSTF-529, Revision 4, Clarify Use and Application Rules ML18346A3582019-02-0505 February 2019 Issuance of Amendments 343 and 325 Regarding the Battery Monitoring and Maintenance Program ML18348A4182019-01-0909 January 2019 Units and 2 Approval of Request for Alternative from Volumetric/Surface Examination Frequency Requirements of ASME Code Case N 729-4 ML18337A3942018-12-11011 December 2018 Proposed Alternative Request for Elimination of the Reactor Pressure Vessel Threads in Flange Examination ML18284A2542018-11-16016 November 2018 Issuance of Amendments Request for Deviation from National Fire Protection Association 805 Requirements ML18249A0192018-11-13013 November 2018 Issuance of Amendment Nos. 341 and 323 Technical Support Center Relocation ML18284A3102018-10-26026 October 2018 Approval of Alternative to the ASME Code Regarding Reactor Vessel Weld Examination - Relief Request ISIR-4-08 ML18131A2532018-07-0606 July 2018 Issuance of Amendments Request for Deviation from National Fire Protection Association 805 Requirements ML18103A0592018-04-19019 April 2018 Request for Use of Alternative Isir 04-05, Revision 1, Associated with Reactor Vessel Closure Head Volumetric/Surface Examination Frequency Requirements for the Inservice Inspection Program ML17312B0302017-12-19019 December 2017 Issuance of Amendments License Amendment Request to Revise Technical Specifications Section 3.7.2, Steam Generator Stop Valves (CAC Nos. MF9539 and MF9540; EPID L-2017-LLA-0198) ML17214A5502017-09-21021 September 2017 Issuance of Amendments License Amendment Request Regarding Technical Specification 3.9.3, Containment Penetrations ML17131A2772017-06-0707 June 2017 Issuance of Amendments License Amendment Request Regarding Containment Leakage Rate Testing Program ML17103A1062017-05-24024 May 2017 Issuance of Amendments Adoption of TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing ML17096A6272017-04-12012 April 2017 Proposed Alternative to Use ASME OM Code Case OMN-20 ML17045A1502017-03-31031 March 2017 Issuance of Amendments Adopting of TSTF0425-A, Revision 3, Relocate Surveillance Frequencies to Licensee Control - RITSTF Initiative 5B ML16327A1102016-12-28028 December 2016 Cover Letter for Revised Safety Evaluation for Amendment Nos. 332 and 314 Adoption of TSTF-490, Rev. 0, and Implementation of Full-Scope Alternative Source Term ML16242A1112016-10-20020 October 2016 DC Cook, Units 1 and 2 - Issuance of Amendments Adoption of TSTF-490,REV.0,Deletion of E-Bar Definition and Revision to Reactor Coolant System Specific Activity Technical Specification and Implementation of Full-Scope Alternative Source Ter ML16216A1812016-08-19019 August 2016 Issuance of Amendment to Revise Technical Specification 3.3.2, Engineered Safety Feature Actuation System Instrumentation ML16195A0042016-08-0404 August 2016 Issuance of Amendments to Revise Technical Specifications to Adopt Technical Specifications Task Force - 523, Generic Letter 2008 01, Managing Gas Accumulation ML16032A0312016-02-0404 February 2016 Request for Use of Alternative REL-PP1 Associated with Pump Inservice Testing (CAC Nos. MF6548 and MF6549) ML15327A2172015-12-11011 December 2015 Issuance of Amendments Technical Specifications Surveillance Requirements 3.8.1.10, 3.8.1.11, and 3.8.1.15 ML14197A0972015-11-30030 November 2015 Issuance of Amendment Regarding Restoration of Normal Reactor Coolant System Pressure and Temperature Consistent with Previously Licensed Conditions 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 2023-01-04
[Table view] Category:Technical Specifications
MONTHYEARML22046A2332022-06-21021 June 2022 Issuance of Amendment Nos. 360 and 342 Regarding Change to the Technical Specification Requirement for Containment Water Level Instrumentation ML21125A5762021-04-19019 April 2021 9 Technical Specification Bases, List of Effective Pages (Unit 2) ML21125A5482021-04-19019 April 2021 2 to Technical Specifications Bases, List of Effective Pages (Unit 1) ML20366A1552021-01-15015 January 2021 Issuance of Amendments Nos. 357 and 336 Regarding Revision to Technical Specifications Bases Control Program ML20329A0012021-01-12012 January 2021 Issuance of Amendment No. 356 Regarding Updating the Reactor Coolant System Pressure-Temperature Limits ML20322A4282021-01-0606 January 2021 Issuance of Amendment Nos. 355 and 335, Revision to Technical Specifications to Adopt Technical Specification Task Force Traveler 567, Revision 1, Add Containment Sump TS to Address GSI-191 Issues AEP-NRC-2020-78, License Amendment Request Regarding a Change to the Steam Generator (SG) Program to Allow for a One-Time Deferral of SG Inspections2020-12-14014 December 2020 License Amendment Request Regarding a Change to the Steam Generator (SG) Program to Allow for a One-Time Deferral of SG Inspections ML19170A3622019-08-0101 August 2019 Issuance of Amendment Approval of Application of Proprietary Leak-Before-Break Methodology for Reactor Coolant System Small Diameter Piping ML17131A2772017-06-0707 June 2017 Issuance of Amendments License Amendment Request Regarding Containment Leakage Rate Testing Program ML16195A0042016-08-0404 August 2016 Issuance of Amendments to Revise Technical Specifications to Adopt Technical Specifications Task Force - 523, Generic Letter 2008 01, Managing Gas Accumulation ML14197A0972015-11-30030 November 2015 Issuance of Amendment Regarding Restoration of Normal Reactor Coolant System Pressure and Temperature Consistent with Previously Licensed Conditions ML15328A4512015-11-19019 November 2015 Enclosures 1 - 5: Affirmation, Description of Proposed Changes, Probabilistic Risk Assessment Technical Adequacy, and CNP Units 1 & 2 TS Pages Marked to Show Proposed Changes ML15187A0022015-07-10010 July 2015 Issuance of Amendment No. 328 (Exigent) Regarding Revision to Technical Specifications for Engineered Safety Feature Actuation System AEP-NRC-2015-62, Exigent License Amendment Request Regarding Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation2015-06-29029 June 2015 Exigent License Amendment Request Regarding Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation ML15076A2262015-04-0606 April 2015 Issuance of Amendments Adoption of TSTF-427, Allowance for Non-Technical Specification Barrier Degradation on Supported System Operability, Revision 2 AEP-NRC-2015-05, Correction of Technical Specification Typographical Error2015-02-0202 February 2015 Correction of Technical Specification Typographical Error ML14282A1182014-11-20020 November 2014 Issuance of Amendments Regarding Containment Divider Barrier Seal AEP-NRC-2014-09, License Amendment Request to Revise Technical Specification Section 5.5.14, Containment Leakage Rate Testing Program2014-03-0707 March 2014 License Amendment Request to Revise Technical Specification Section 5.5.14, Containment Leakage Rate Testing Program ML13282A2142013-10-0909 October 2013 Issuance of Amendment Revision to Technical Specification 3.6.9, Distributed Ignition System (Dis) (Emergency Circumstances) AEP-NRC-2013-79, License Amendment Request Regarding Restoration of Normal Reactor Coolant System Operating Pressure and Temperature Consistent with Previously Licensed Conditions, with Enclosures 1 Through 52013-10-0808 October 2013 License Amendment Request Regarding Restoration of Normal Reactor Coolant System Operating Pressure and Temperature Consistent with Previously Licensed Conditions, with Enclosures 1 Through 5 ML11182A1782011-07-28028 July 2011 License Amendment, Issuance of Amendments Cyber Security Plan AEP-NRC-2009-71, Response to Request for Additional Information Regarding a License Amendment Request Associated with the Large-Break Loss-of-Coolant Accident Analysis Methodology2009-11-20020 November 2009 Response to Request for Additional Information Regarding a License Amendment Request Associated with the Large-Break Loss-of-Coolant Accident Analysis Methodology AEP-NRC-2009-23, License Amendment Request Regarding Large Break Loss-of-Coolant Accident Analysis Methodology2009-03-19019 March 2009 License Amendment Request Regarding Large Break Loss-of-Coolant Accident Analysis Methodology ML0903502102009-01-14014 January 2009 License Amendment Request to Revise Operating Licenses DPR-58 and DPR-74, Appendix B, Environmental Technical Specifications, Part II, Non-Radiological Environmental Protection Plan ML0826004692008-09-0404 September 2008 Supplement to Emergency Diesel Generator Maximum Steady State Frequency Amendment Request ML0815108932008-05-28028 May 2008 Correction of Amendment No. 304 for Unit 1 and 287 for Unit 2, (Tac Nos. MD6317 & MD6318) - Tech Specs ML0812302692008-04-28028 April 2008 Tech Spec Pages for Amendments 305 and 288 Regarding Maximum Ventilation System Filter Pressure Drop ML0812302702008-04-28028 April 2008 Tech Spec Pages for Amendments 304 & 287 to Add a Surveillance Requirement for When Offsite Power Is Provided Via Backfeed Through the Main Transformer and a Unit Auxiliary Transformer ML0806600672008-03-0505 March 2008 Tech Spec Page for Amendments 302 & 285 to Revise a Specification Inadvertently Omitted by Previous Amendments Power Range Neutron Flux High Negative Rate Trip Function ML0801106652008-01-11011 January 2008 Tech Spec Pages for Amendments 301 and 284 Regarding Operational Test of the Reactor Trip on Turbine Trip ML0800800492008-01-0404 January 2008 Technical Specifications, Correction of Amendment No. 282 Containment Sump Modifications Per Generic Letter 2004-02 ML0735204032007-12-17017 December 2007 Technical Specifications, Issuance of Amendment RTS and ESFAS Bypass Testing Capability ML0729501002007-10-18018 October 2007 Technical Specifications, Issuance of Amendments Containment Sump Modifications Per Generic Letter 2004-02 (TAC Nos. MD5901 & MD5902) ML0725306592007-09-19019 September 2007 Technical Specifications, Issuance of Amendment Replacement of Resistance - Temperature Detectors and Associated Piping ML0714200712007-05-11011 May 2007 Technical Specification Change of Conditional Surveillance Frequency ML0710100972007-04-0606 April 2007 Technical Specification Page Correction of Administrative Error in Amendment No. 298, Steam Generator Tube Integrity ML0708607652007-03-14014 March 2007 Corrections to Technical Specification Table of Contents ML0708101332007-03-14014 March 2007 D.C. Cook, Technical Specifications, Steam Generator Integrity ML0700305172006-12-26026 December 2006 Supplement to Application for Technical Specification (TS) Improvement Regarding Steam Generator Tube Integrity ML0628303132006-10-0606 October 2006 D.C. Cook, Tech Spec Pages for Amendment 296, Regarding Elimination of the Resistance Temperature Detector (RTD) Bypass Loop ML0624901142006-09-0101 September 2006 D.C. Cook, Technical Specification Pages Re AC Sources - Operating ML0618801572006-07-0505 July 2006 Technical Specifications Pages Regarding Leakage ML0616004492006-05-31031 May 2006 Application for Amendment to Revise Technical Specification Surveillance Requirement for Channel Calibration of Overtemperature Differential Temperature and Overpower Differential Temperature Reactor Protection System Functions ML0610805842006-04-21021 April 2006 Correction of Amendments Technical Specifications, Conversion to Improved Format ML0610404022006-04-13013 April 2006 Technical Specification - Issuance of Amendment Under Emergency Circumstances Regarding Diesel Generator Votage Limit Requirements ML0607603742006-03-0707 March 2006 Application for Amendment to Revise Technical Specification 5.5.2, Leakage Monitoring Program. ML0604400222006-02-10010 February 2006 Technical Specifications, Delete the Power Range Neutron Flux High Negative Rate Trip Function ML0601700302006-01-12012 January 2006 Tech Spec Pages for Amendments 292 and 274 Regarding Elimination of Requirements for Monthly Operating Reports and Occupational Radiation Exposure Reports ML0527303202005-09-30030 September 2005 Tech Spec Pages for Amendments 291 and 273 Safety Evaluation Regarding Allowed Outage Time Extension for the Emergency Diesel Generators ML0526900432005-09-23023 September 2005 Tech Spec Pages for Amendments 290 and 272 Requirements of Improved Technical Specification Surveillance Requirement 3.8.1.8 with the Wording of Previous Technical Specification SR 4.8.1.1.2.e.11 with Minor Editorial.. 2022-06-21
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Mr. Lawrence J. Weber Senior Vice President and Chief Nuclear Officer UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 November 20, 2014 Indiana Michigan Power Company Nuclear Generation Group One Cook Place Bridgman, Ml 49106 SUBJECT: DONALD C. COOK NUCLEAR PLANT, UNITS 1 AND 2 -ISSUANCE OF AMENDMENTS REGARDING CONTAINMENT DIVIDER BARRIER SEAL RE: (TAC NOS. MF3052 AND MF3053) Dear Mr. Weber: The U.S. Nuclear Regulatory Commission has issued the enclosed Amendment No. 324 to Renewed Facility Operating License No. DPR-58 and Amendment No. 307 to Renewed Facility Operating License No. DPR-7 4 for the Donald C. Cook Nuclear Plant, Units 1 and 2. The amendments consist of changes to the technical specifications (TSs) in response to your application dated November 6, 2013, as supplemented by letters dated June 13, 2014, and August 15, 2014. The amendments would revise TS 3.6.13, "Divider Barrier Integrity", Surveillance Requirement 3.6.13.5 for the divider barrier seal inspection for the Donald C. Cook Nuclear Plant, Units 1 and 2.
-2-A copy of our related safety evaluation is also enclosed. A Notice of Issuance will be included in the Commission's biweekly Federal Register notice. Docket Nos. 50-315 and 50-316 Enclosures: 1. Amendment No. 324 to DPR-58 2. Amendment No. 307 to DPR-74 3. Safety Evaluation cc w/encls: Distribution via ListServ Sincerely, Mahesh Chawla, Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 INDIANA MICHIGAN POWER COMPANY DOCKET NO. 50-315 DONALD C. COOK NUCLEAR PLANT. UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No.324 License No. DPR-58 1. The U.S. Nuclear Regulatory Commission (the Commission) has found that: A. The application for amendment by Indiana Michigan Power Company (the licensee) dated November 6, 2013, as supplemented by letters dated June 13, 2014, and August 15, 2014, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied. 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. DPR-58 is hereby amended to read as follows: (2) Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 324, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan. Enclosure 1
-2-3. This license amendment is effective as of its date of issuance and shall be implemented within 90 days. Attachment: FOR THE NUCLEAR REGULATORY COMMISSION L Pelton, Chief Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Changes to the Technical Specifications Date of Issuance: November 20, 2014 ATTACHMENT TO LICENSE AMENDMENT NO. 324 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-58 DOCKET NO. 50-315 Replace the following page of Renewed Facility Operating License DPR-58 with the attached revised page. The revised page is identified by amendment number and contains a marginal line indicating the area of change. REMOVE INSERT 3 3 Replace the following pages of Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change. REMOVE INSERT 3.6.13-2 3.6.13-2
-3-and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument and equipment calibration or associated with radioactive apparatus or components; and (5) Pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility. C. This renewed operating license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter 1: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below: (1) Maximum Power Level The licensee is authorized to operate the facility at steady state reactor core power levels not to exceed 3304 megawatts thermal in accordance with the conditions specified herein. (2) Technical Specifications The Technical Specifications contained in Appendix A, and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 324, are hereby incorporated in this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan. (3) Less than Four Loop Operation The licensee shall not operate the reactor at power levels above P-7 (as defined in Table 3.3.1-1 of Specification 3.3.1 of Appendix A to this renewed operating license) with less than four reactor coolant loops in operation until (a) safety analyses for less than four loop operation have been submitted, and (b) approval for less than four loop operation at power levels above P-7 has been granted by the Commission by amendment of this license. (4) Fire Protection Program Indiana Michigan Power Company shall implement and maintain in effect all provisions of the approved fire protection program that comply with 10 CFR 50.48(a) and 10 CFR 50.48(c), as specified in the licensee's amendment request dated July 1, 2011, as supplemented by letters dated September 2, 2011, April 27, 2012, June 29, 2012, August 9, 2012, October 15, 2012, November 9, 2012, January 14, 2013, February 1, 2013, Renewed License No. DPR-58 Amendment No. 324 SURVEILLANCE REQUIREMENTS SR 3.6.13.1 SR 3.6.13.2 SR 3.6.13.3 SR 3.6.13.4 SR 3.6.13.5 SURVEILLANCE Verify, by visual inspection, all personnel access doors and equipment hatches between upper and lower containment compartments are closed. Verify, by visual inspection, that the seals and sealing surfaces of each personnel access door and equipment hatch have: a. No detrimental misalignments; b. No cracks or defects in the sealing surfaces; and c. No apparent deterioration of the seal material. Verify, by visual inspection, each personnel access door or equipment hatch that has been opened for personnel transit entry is closed. Remove two divider barrier seal test coupons and verify: a. Both test coupons' tensile strength is 120 psi; and b. Both test coupons' elongation is<:: 100%. Visually inspect 95% of the divider barrier seal length, and verify: a. Seal and seal mounting connections are installed such that the total divider barrier bypass area is maintained within design limits; and b. Seal material shows no evidence of deterioration due to holes, ruptures, chemical attack, abrasion, radiation damage, or changes in physical appearance. Divider Barrier Integrity 3.6.13 FREQUENCY Prior to entering MODE 4 from MODE5 Prior to final closure after each opening AND Only required for seals made of resilient materials 10 years After each opening 24 months 24 months Cook Nuclear Plant Unit 1 3.6.13-2 Amendment No. 237-, 324 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 INDIANA MICHIGAN POWER COMPANY DOCKET NO. 50-316 DONALD C. COOK NUCLEAR PLANT, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 307 License No. DPR-7 4 1. The U.S. Nuclear Regulatory Commission (the Commission) has found that: A. The application for amendment by Indiana Michigan Power Company (the licensee) dated November 6, 2013, as supplemented by letters dated June 13, 2014, and August 15, 2014, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied. 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. DPR-74 is hereby amended to read as follows: (2) Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 307, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan. Enclosure 2
-2 -3. This license amendment is effective as of its date of issuance and shall be implemented within 90 days. Attachment: NUCLEAR REGULATORY COMMISSION avid L. Pel on, Chief Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Changes to the Technical Specifications Date of Issuance: November 20, 2014 ATTACHMENT TO LICENSE AMENDMENT N0.307 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-74 DOCKET NO. 50-316 Replace the following page of Renewed Facility Operating License DPR-74 with the attached revised page. The revised page is identified by amendment number and contains a marginal line indicating the area of change. REMOVE INSERT 3 3 Replace the following pages of Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change. REMOVE INSERT 3.6.13-2 3.6.13-2
-3 -radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument and equipment calibration or associated with radioactive apparatus or components; and (5) Pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility. C. This renewed operating license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter 1: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below: (1) Maximum Power Level The licensee is authorized to operate the facility at steady state reactor core power levels not to exceed 3468 megawatts thermal in accordance with the conditions specified herein and in Attachment 1 to the renewed operating license. The preoperational tests, startup tests and other items identified in Attachment 1 to this renewed operating license shall be completed. Attachment 1 is an integral part of this renewed operating license. (2) Technical Specifications The Technical Specifications contained in Appendix A, and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 307, I are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan. (3) ,Additional Conditions (a) Deleted by Amendment No. 76 (b) Deleted by Amendment No.2 (c) Leak Testing of Emergency Core Cooling System Valves Indiana Michigan Power Company shall prior to completion of the first inservice testing interval leak test each of the two valves in series in the Renewed License No. DPR-74 Amendment No. 307 SURVEILLANCE REQUIREMENTS SR 3.6.13.1 SR 3.6.13.2 SR 3.6.13.3 SR 3.6.13.4 SR 3.6.13.5 SURVEILLANCE Verify, by visual inspection, all personnel access doors and equipment hatches between upper and lower containment compartments are closed. Verify, by visual inspection, that the seals and sealing surfaces of each personnel access door and equipment hatch have: a. No detrimental misalignments; b. No cracks or defects in the sealing surfaces; and c. No apparent deterioration of the seal material. Verify, by visual inspection, each personnel access door or equipment hatch that has been opened for personnel transit entry is closed. Remove two divider barrier seal test coupons and verify: a. Both test coupons' tensile strength is 2:: 120 psi; and b. Both test coupons' elongation 100%. Visually inspect 2:: 95% of the divider barrier seal length, and verify: a. Seal and seal mounting connections are installed such that the total divider barrier bypass area is maintained within design limits; and b. Seal material shows no evidence of deterioration due to holes, ruptures, chemical attack, abrasion, radiation damage, or changes in physical appearance. Divider Barrier Integrity 3.6.13 FREQUENCY Prior to entering MODE 4 from MODES Prior to final closure after each opening AND Only required for seals made of resilient materials 10 years After each opening 24 months 24 months Cook Nuclear Plant Unit 2 3.6.13-2 Amendment No. 269, 307 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 324 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-58 AND AMENDMENT NO. 307 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-74 INDIANA MICHIGAN POWER COMPANY DONALD C. COOK NUCLEAR PLANT. UNITS 1 AND 2 DOCKET NOS. 50-315 AND 50-316 1.0 INTRODUCTION By application dated November 6. 2013 (Agencywide Documents Access and Management System (ADAMS Accession No. ML 13312A006), pursuant to Section 50.90 of Title 10 of the Code of Federal Regulations (CFR), Indiana Michigan Power Company (I&M, or licensee) submitted a license amendment request (LAR) for changes to Donald C. Cook Nuclear Plant (CNP) Units 1 and 2 technical specifications (TSs). The licensee's proposed change would revise TS 3.6.13, Divider Barrier Integrity, and Surveillance Requirement (SR) 3.6.13.5 for the divider barrier seal inspection. The licensee's letter dated November 6, 2013, was supplemented by letters dated June 13, 2014 (ADAMS Accession No. ML 14167A374), and August 15, 2014 (ADAMS Accession No. ML 14230A678), which provided responses to the U.S. Nuclear Regulatory Commission (NRC) staff's requests for additional information (RAis). The supplemental letters dated June 13, 2014, and August 15, 2014, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the staff's original proposed no significant hazards consideration determination as published in the Federal Register on February 19, 2014 (79 FR 9496). 2.0 REGULATORY EVALUATION The regulation at 10 CFR Section 50.36(c)(3), "Surveillance requirements" states: Surveillance requirements are requirements relating to test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the limiting conditions for operation will be met. Enclosure 3
-2-The licensee states "The construction permits for CNP were issued and the majority of construction was completed prior to issuance of 10 CFR 50, Appendix A, General Design Criteria" and "CNP was designed and constructed to comply with the Atomic Energy Commission (AEC) General Design Criteria (GDC) as proposed on July 10, 1967". Therefore the licensee will be complying with the AEC proposed General Design Criteria to the CNP which is contained in the CNP Updated Final Safety Analysis Report (UFSAR) as the Plant Specific Design Criteria (PSDC) and differs from Appendix A of 10 CFR Part 50 GDC in both numbering and content. The PSDC applicable to this LAR are discussed below: PSDC 10 Reactor Containment The CNP UFSAR states: The containment structure shall be designed (a) to sustain without undue risk to the health and safety of the public the initial effects of gross equipment failures, such as a large reactor coolant pipe break, without loss of required integrity, and (b) together with other engineered safety features as may be necessary, to retain for as long as the situation requires the functional capability of the containment to the extent necessary to avoid undue risk to the health and safety of the public. PSDC 49 Reactor Containment Design Basis The CNP UFSAR states: The reactor containment structure, including openings and penetrations, and any necessary containment heat removal systems, shall be designed so that the leakage of radioactive materials from the containment structure under conditions of pressure and temperature resulting from the largest credible energy release following a loss-of-coolant accident, including the calculated energy from water or other chemical reactions that could occur as a consequence of failure of any single active component in the emergency core cooling system will not result in undue risk to the health and safety of the public. 3.0 TECHNICAL EVALUATION CNP Units 1 and 2 containment buildings are reinforced concrete structures consisting of a vertical cylinder, a hemispherical dome, and a flat base slab. A steel liner is attached to the inside face of the concrete (shell, dome, and the base slab); the interior of the containment structure is divided into three compartments:
- An intermediate compartment that houses the energy absorbing ice bed (ice condenser compartment); and
-3 -* An upper compartment that accommodates the air displaced from the other two compartment volumes during an accident condition. The ice condenser is an insulated cold storage room in which ice is contained in a vertical cylindrical column. In an accident scenario, lower inlet doors located below the operating deck at the bottom of the ice condenser open due to the rise in pressure in the lower compartment. This allows steam to flow from the lower compartment into the ice condenser compartment. The steam is condensed as it enters the ice condenser compartment, thus limiting the peak pressure in the containment. The divider barrier between the upper and lower containment compartment is designed to carry the differential pressure between the lower and upper compartments during the postulated of-coolant accident. The divider barrier seal provides a pressure boundary between the lower and upper containment compartments of the containment structure and is located on the boundary of these compartments. The divider barrier seal is a structurally mounted flexible seal backed up by a steel plate that prevents the flow of steam and air from bypassing the ice condenser. The licensee's submitted amendment proposes to revise the SR 3.6.13.5.a as follows: Current SR 3.6.13.5.a: "Seal and seal mounting bolts are properly installed; and" Revised SR 3.6.13.5.a: "Seal and seal mounting connections are installed such that the total divider barrier bypass area is maintained within design limits; and" The proposed change to the SR 3.6.15.5.a involves two changes. The first proposed change to the SR replaces the word "bolts" with the word "connections". In an RAI, the NRC staff requested the licensee describe the types of connections and the procedure that will be used for verifying acceptable installation of these connections. On June 13, 2014, the licensee provided a response to SCVB-RAI-2 (ADAMS Accession No. ML 14167A374), stating the following: Procedures for performing the divider barrier seal surveillance contain design configuration criteria for the proper/acceptable installation of these connections. The criteria specified by the surveillance procedures include: bolt spacing, edge distances, number of connections, and tightness. The licensee also provided a response to STSB RAI-1C (ADAMS Accession No. ML 14167A374), stating the following: Seal mounting connections currently holding the divider barrier seal in place include bolts, screws, welded studs, nuts, welds, and concrete anchors. These connections are not specifically described in the UFSAR but are described on various CNP controlled design drawings, including but not limited to 1-2-3207E, 1-2-3207F, and 1-AEQS-226-A.
-4-Based on the NRC staff's review of the licensee's responses to SCVB-RAI-2 and STSB RAI-1 C, (ADAMS Accession No. ML 14167A374), the staff finds that the proposed change to the SR replacing the word "bolts" with the word "connections" is acceptable because the licensee describes connections used in CNP controlled design drawings in 1-2-3207E, 1-2-3207F, and 1-AEQS-226-A. Further, the licensee explains that they have procedures in place for performing the divider barrier seals surveillance for the acceptable installation of these connections. The proposed change to the SR 3.6.13.5.a also includes the requirement that the installed connections should maintain the total divider bypass area within the design limits. In RAI-3, the licensee was requested to describe the NRC-approved methodology that will be used to determine that the acceptance criteria for the bypass area are met. In a letter dated June 13, 2014 (ADAMS Accession No. ML 14167A374), the licensee stated the following: In case deficient connections are discovered, then the resulting divider barrier bypass would be determined, using an accepted standard, the American Institute of Steel Construction (AISC) Manual of Steel Construction, (tables for beam diagrams and formulas), as referenced in Updated Final Safety Analysis Report (UFSAR) Chapter 5, or using a simplified method that is more conservative, to determine the deflections of the as found configurations due to a postulated blowdown, and these deflections would be used to quantify the bypass area. The total bypass area for that unit is then compared against the Allowable Design Basis Bypass Area of seven square feet, per UFSAR 5.3.5.15.4. The assumed Analysis Value is 35 square feet, per UFSAR 14.3.4.1.3.1.1.e. After reviewing the above response, the NRC staff requested the licensee to explain: simplified method that is more conservative to determine the deflections of the as found configurations." More specifically, the licensee was requested to discuss the simplified method, the standard on which it is based, and the conservatism in the method. In a letter dated August 15, 2014 (ADAMS Accession No. ML 14230A678), the licensee stated, in part: "The simplified method is also based on the AISC standard." The licensee provided a pictorial drawing describing two cantilever beams, each attached at one end, with a uniformly distributed load (as referenced in the AISC Manual of Steel Construction 7th edition) to determine the assumed divider barrier bypass area. The NRC staff finds the licensee's responses acceptable because the assumed bypass area derived by using the simplified method based upon the pictorial drawing (two cantilever beams) would be approximately three times larger than the bypass area calculated by the exact AISC structural analysis method based on the fixed beam and thus would be more conservative. Based on its review, the staff finds that the proposed change meets the requirements of PSDC contained in the licensee's UFSAR, (1) PSDC 10, because the licensee showed that the containment design structure important to safety are not exceeded during an accident. The staff also finds that the proposed change meets the requirements of PSDC contained in UFSAR, (2) PSDC 49, because the licensee showed that the reactor containment structure and penetrations, with the aid of containment heat removal systems including the ice bed, are designed to limit radioactive fission products from the containment below 10 CFR 100 values. In addition, the NRC staff determined that the proposed modification does not change the intent of the surveillance requirements in SR 3.6.13.5.a and that the licensee will continue to meet the
-5 -requirements in 10 CFR 50.36(c)(3). Therefore, the NRC staff finds the proposed license amendment to be acceptable. 4.0 STATE CONSULTATION In accordance with the Commission's regulations, the Michigan State official was notified of the proposed issuance of the amendments. The State official had no comments. 5.0 ENVIRONMENTAL CONSIDERATION The amendments change the requirements with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 or change the surveillance requirements. The NRC staff has determined that the amendments involve no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendments involve no significant hazards consideration and there has been no public comment on such finding (79 FR 9496). Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments. 6.0 CONCLUSION The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) there is reasonable assurance that such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public. Principal Contributor: Samina Shaikh Date: November 20, 2014
-2-A copy of our related safety evaluation is also enclosed. A Notice of Issuance will be included in the Commission's biweekly Federal Register notice. Docket Nos. 50-315 and 50-316 Enclosures: 1. Amendment No. 324 to DPR-58 2. Amendment No. 307 to DPR-74 3. Safety Evaluation cc w/encls: Distribution via ListServ DISTRIBUTION: PUBLIC LPL3-1 r/f Sincerely, IRA/ Mahesh Chawla, Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation RidsNrrPMDCCook Resource RidsNrrLAMHendersonResource RidsNrrDoriDprResource SShaikh, NRR RidsOgcRp Resource RidsNrrDoriDprResource RidsRgn3MaiiCenter Resource RidsNrrDoriLpl3-1 Resource RidsNrrDssScvb Resource RidsAcrsAcnw_MaiiCTR Resource RidsNrrDssStsb Resource ADAMS ACCESSION N ML14282A118 * . d d t d A 27 2014 o.: v1a memoran urn ae ugust ' OFFICE NRR/LPL3-1/PM NRR/LPL3-1/LA DSS/SCVB/BC DSS/STSB/BC NAME MChawla (TBeltz for) MHenderson RDennig
- REIIiott DATE 10/22/14 10/23/14 08/27/14 11/02/14 OFFICE OGC NRR/LPL3-1/BC NRR/LPL3-1/PM NAME A Ghosh DPelton MChawla DATE 11/19/14 11/20/14 11/20/14 OFFICIAL RECORD COPY