ML21034A155
From kanterella
Letter Sequence Approval | |
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EPID:L-2020-LLR-0133, ASME Code Case N-729-6 (Approved, Closed) | |
Initiation Administration Questions
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MONTHYEARAEP-NRC-2020-71, Indiana Michigan Power Co., Supplement to Request for Relief Related to American Society of Mechanical Engineers (Asme)Code Case N-729-6 Supplemental Examination Requirements, ISIR-5-042020-10-0909 October 2020
[Table View]Indiana Michigan Power Co., Supplement to Request for Relief Related to American Society of Mechanical Engineers (Asme)Code Case N-729-6 Supplemental Examination Requirements, ISIR-5-04 Project stage: Supplement ML20289A1192020-10-0909 October 2020 NRR E-mail Capture - D.C. Cook Nuclear Plant Unit Nos. 1 and 2 - Acceptance of Relief Request for Alternative to N-729-4 for RPV Head Visual Examination Project stage: Acceptance Review ML20290A4252020-10-15015 October 2020 Verbal Authorization of Relief Request ISIR-5-04 Regarding Alternative to N-729-6 for RPV Head Visual Examination Project stage: Approval ML20289A7122020-10-15015 October 2020 NRR E-mail Capture - D.C. Cook Nuclear Plant Unit No. 1 - Verbal Authorization of Relief Request ISIR-5-04 Regarding Alternative to N-729-6 for RPV Head Visual Examination Project stage: Approval 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 Project stage: Approval 2020-10-09 |
| ML21034A155 | |
| Person / Time | |
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| Site: | Cook  |
| Issue date: | 02/12/2021 |
| From: | Nancy Salgado Plant Licensing Branch III |
| To: | Gebbie J Indiana Michigan Power Co |
| Wall S | |
| References | |
| EPID L-2020-LLR-0133 | |
| Download: ML21034A155 (8) | |
Similar Documents at Cook | |
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Category:Code Relief or Alternative
MONTHYEARML22363A5622023-01-0404 January 2023
[Table view]Relief Request ISIR-5-06 Related to ASME Code Case N-729-6 Supplemental Examination Requirements of Reactor Vessel Closure Head Penetration Nozzles 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)) 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 ML20290A4252020-10-15015 October 2020 Verbal Authorization of Relief Request ISIR-5-04 Regarding Alternative to N-729-6 for RPV Head Visual Examination AEP-NRC-2020-65, Request for Relief Related to American Society of Mechanical Engineers (ASME) Code Case N-729-6 Supplemental Examination Requirements, ISIR-5-042020-10-0505 October 2020 Request for Relief Related to American Society of Mechanical Engineers (ASME) Code Case N-729-6 Supplemental Examination Requirements, ISIR-5-04 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 ML19196A0642019-08-23023 August 2019 Relied Request ISIR-4-10 Regarding Fourth Inservice Inspection Program Interval ML18284A3102018-10-26026 October 2018 Approval of Alternative to the ASME Code Regarding Reactor Vessel Weld Examination - Relief Request ISIR-4-08 AEP-NRC-2018-33, Proposed Alternative Request for Elimination of the Reactor Pressure Vessel Threads in Flange Examination2018-06-14014 June 2018 Proposed Alternative Request for Elimination of the Reactor Pressure Vessel Threads in Flange Examination AEP-NRC-2018-20, Request for Alternative from Volumetric/Surface Examination Frequency Requirement of ASME Code Case N-729-4, Request Number Isir 04-5, Revision 12018-03-14014 March 2018 Request for Alternative from Volumetric/Surface Examination Frequency Requirement of ASME Code Case N-729-4, Request Number Isir 04-5, Revision 1 ML17096A6272017-04-12012 April 2017 Proposed Alternative to Use ASME OM Code Case OMN-20 ML16054A5722016-03-0404 March 2016 Relief Request REL-002 Associated with Valve Seat Leakage Testing ML15299A0482015-10-29029 October 2015 Alternative Isir 4-06 to the Requirements of the ASME Code AEP-NRC-2015-31, Submittal of 10 Cer 50.55a Requests Associated with the Fifth Ten-Year Inservice Testing Interval2015-07-31031 July 2015 Submittal of 10 Cer 50.55a Requests Associated with the Fifth Ten-Year Inservice Testing Interval ML15156A9062015-06-11011 June 2015 Request for Use of Alternative Isir 04-02 Associated with Reactor Vessel Closure Head Volumetric/Surface Examination Frequency Requirements for the Inservice Inspection Program AEP-NRC-2011-23, Relief Requests for Limited Coverage Examinations Performed in the Third 10-Year Inspection Interval2011-04-0808 April 2011 Relief Requests for Limited Coverage Examinations Performed in the Third 10-Year Inspection Interval AEP-NRC-2009-52, Third and Fourth Ten-Year Interval Inservice Inspection Program Relief Request ISIR-312009-08-21021 August 2009 Third and Fourth Ten-Year Interval Inservice Inspection Program Relief Request ISIR-31 AEP-NRC-2009-26, Request to Extend the Inservice Inspection Interval for Reactor Vessel Weld Examination - Relief Request ISIR-302009-02-27027 February 2009 Request to Extend the Inservice Inspection Interval for Reactor Vessel Weld Examination - Relief Request ISIR-30 ML0903300652009-02-18018 February 2009 Relief Requests ISIR-23, ISIR-24 and ISIR-25 on End-of-Interval System Pressure Testing of Class 1 Components ML0830102372008-10-0707 October 2008 Relief Requests for Reactor Vessel Shell-to-Flange, and Nozzle to Safe-end Weld Examination AEP-NRC-2008-25, Use of Weld Inlays as an Alternative Repair Technique for Reactor Vessel Safe End-to-Primary Nozzle Alloy 82/182 Welds2008-10-0707 October 2008 Use of Weld Inlays as an Alternative Repair Technique for Reactor Vessel Safe End-to-Primary Nozzle Alloy 82/182 Welds ML0634200332006-12-29029 December 2006 Correction of Safety Evaluation Associated with Authorization of an Alternative ML0617301752006-06-28028 June 2006 D.C. Cook, Relief, Relief Requests for the Fourth 10-Year Pump and Valve Inservice Testing Program Interval ML0616403122006-06-0202 June 2006 Fourth 10-Year Interval Pump and Valve Inservice Testing Program - Request for Additional Information ML0607606732006-04-0303 April 2006 Relief Request REL-PP6 Regarding the West Essential Service Water Pump Test Frequency ML0603206912006-02-16016 February 2006 Alternatives Regarding Requirements for Examination of Dissimilar Metal Piping Welds ML0526503262005-09-13013 September 2005 Proposed Alternative to the American Society of Mechanical Engineers Code, Section XI Repair Requirements ML0517200062005-06-27027 June 2005 6/27/05, D.C. Cook, Unit 1, Alternative to Repair Requirements of Section XI of the American Society of Mechanical Engineers Code ML0307708822003-04-0202 April 2003 DC Cook, Units 1 & 2, Relief, Use of Alternatives to Pressure Retaining Bolting Inspection Requirements of American Society of Mechanical Engineers Boiler and Pressure Vessel Code Relief Isir 11 Thru 13, MB6352, MB6353, MB6354, MB6355, MB63 2023-01-04 Category:Letter MONTHYEARAEP-NRC-2024-79, Unit 2, Independent Spent Fuel Storage Installation - Registration of Dry Spent Storage Cask2024-09-26026 September 2024
[Table view]Unit 2, Independent Spent Fuel Storage Installation - Registration of Dry Spent Storage Cask AEP-NRC-2024-78, Reply to a Notice of Violation: EA-24-0472024-09-23023 September 2024 Reply to a Notice of Violation: EA-24-047 05000316/LER-2024-002, Manual Reactor Trip Following Rapid Downpower for Steam Leak2024-09-12012 September 2024 Manual Reactor Trip Following Rapid Downpower for Steam Leak IR 05000315/20244022024-09-10010 September 2024 Security Baseline Inspection Report 05000315/2024402 and 05000316/2024402, Independent Spent Fuel Storage Installation Security Inspection Report 07200072/2024401 AEP-NRC-2024-69, Core Operating Limits Report2024-09-0909 September 2024 Core Operating Limits Report IR 05000315/20243012024-09-0505 September 2024 NRC Initial License Examination Report 05000315/2024301 and 05000316/2024301 ML24225A0022024-09-0303 September 2024 Issuance of Amendment Nos. 363 and 344 Revising Technical Specifications Section 3.8.1, AC Sources-Operating, for a One-Time Extension of a Completion Time IR 05000315/20240112024-08-30030 August 2024 NRC Inspection Report 05000315/2024011 and 05000316/2024011 and Notice of Violation AEP-NRC-2024-51, Annual Report of Loss-Of-Coolant Accident Evaluation Model Changes2024-08-28028 August 2024 Annual Report of Loss-Of-Coolant Accident Evaluation Model Changes AEP-NRC-2024-76, Unit 2 - Supplement to License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating2024-08-28028 August 2024 Unit 2 - Supplement to License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating 05000316/LER-2024-003, Plant Shutdown Required by Technical Specifications Due to Reactor Coolant System Identified Leakage2024-08-22022 August 2024 Plant Shutdown Required by Technical Specifications Due to Reactor Coolant System Identified Leakage IR 05000315/20240052024-08-21021 August 2024 Updated Inspection Plan for Donald C. Cook Nuclear Plant, Units 1 and 2 (Report 05000315/2024005 and 05000316/2024005) AEP-NRC-2024-61, Unit 2 - Response to Request for Additional Information for Neutron Flux Instrumentation License Amendment Request2024-08-15015 August 2024 Unit 2 - Response to Request for Additional Information for Neutron Flux Instrumentation License Amendment Request ML24221A2702024-08-0808 August 2024 Unit 2 Independent Spent Fuel Storage Installation - Registration of Dry Spent Fuel Storage Cask AEP-NRC-2024-62, Unit 2, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Cask2024-08-0707 August 2024 Unit 2, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Cask ML24256A1482024-08-0202 August 2024 2024 Post Examination Submittal Letter AEP-NRC-2024-47, Form OAR-1, Owners Activity Report2024-07-30030 July 2024 Form OAR-1, Owners Activity Report ML24183A0162024-07-25025 July 2024 Review of Reactor Vessel Material Surveillance Program Capsule W Technical Report ML24169A2142024-07-25025 July 2024 Issuance of Amendment No. 362 Regarding Change to Technical Specification 3.4.12, Low Temperature Overpressure Protection System IR 05000315/20240022024-07-24024 July 2024 Integrated Inspection Report 05000315/2024002 and 05000316/2024002 ML24197A1262024-07-15015 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-2024-52, Manual Reactor Trip Following Rapid Downpower for Steam Leak2024-07-15015 July 2024 Manual Reactor Trip Following Rapid Downpower for Steam Leak ML24191A0692024-07-0909 July 2024 Operator Licensing Examination Approval - Donald C. Cook Nuclear Power Plant, July 2024 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 ML24176A1012024-06-21021 June 2024 57143-EN 57143 - Paragon Energy Solutions - Update 1 (Final) - 10CFR Part 21 Final Notification: P21-05242024-FN, Rev. 0 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 ML24163A0132024-06-12012 June 2024 Request for Information for the NRC Age-Related Degradation Inspection: Inspection Report 05000315/2024012 and 05000316/2024012 AEP-NRC-2024-23, Core Operating Limits Report2024-05-23023 May 2024 Core Operating Limits Report ML24141A2162024-05-20020 May 2024 —Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection AEP-NRC-2024-30, Reactor Trip Due to Main Turbine Trip from a High-High Thrust Bearing Position Trip2024-05-20020 May 2024 Reactor Trip Due to Main Turbine Trip from a High-High Thrust Bearing Position Trip 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 IR 05000315/20240012024-05-14014 May 2024 Integrated Inspection Report 05000315/2024001 and 05000316/2024001 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 IR 05000315/20244012024-05-14014 May 2024 – Security Baseline Inspection Report 05000315/2024401 and 05000316/2024401 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-2024-24, Form OAR-1, Owners Activity Report2024-05-0707 May 2024 Form OAR-1, Owners Activity Report ML24115A2152024-05-0707 May 2024 LTR: CNP Non-Acceptance with Opportunity TS 3-8-1 ML24256A1472024-05-0606 May 2024 DC Cook 2024 NRC Examination Submittal Letter: Submittal ML24116A0002024-05-0202 May 2024 – Regulatory Audit in Support of Review of the Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors 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-2024-02, 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-2024-29, (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-2024-19, 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 ML24073A2342024-03-0606 March 2024 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors IR 05000315/20230062024-02-28028 February 2024 Annual Assessment Letter for Donald C. Cook Nuclear Plant, Units 1 and 2 (Report 05000315/2023006 and 05000316/2023006) 2024-09-09 Category:Safety Evaluation MONTHYEARML24225A0022024-09-0303 September 2024
[Table view]Issuance of Amendment Nos. 363 and 344 Revising Technical Specifications Section 3.8.1, AC Sources-Operating, for a One-Time Extension of a Completion Time ML24169A2142024-07-25025 July 2024 Issuance of Amendment No. 362 Regarding Change to Technical Specification 3.4.12, Low Temperature Overpressure Protection System ML24107B1202024-04-18018 April 2024 Authorization and Safety Evaluation for Alternative Request No. ISIR-5-07 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 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) 2024-09-03 |
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