ML19196A064
From kanterella
Revision as of 15:40, 5 September 2019 by StriderTol (talk | contribs) (Created page by program invented by StriderTol)
Letter Sequence Other | |
|---|---|
EPID:L-2019-LLR-0054, Proposed Alternative Request for Reactor Vessel Inspections to Meet Code Requirements for Two ISI Intervals (Open) | |
Administration Questions
| |
MONTHYEARML19099A3272019-04-0202 April 2019
[Table View]DC Cook ISI 10 Year Interval Layout Project stage: Request AEP-NRC-2019-24, Proposed Alternative Request for Reactor Vessel Inspections to Meet Code Requirements for Two ISI Intervals2019-05-30030 May 2019 Proposed Alternative Request for Reactor Vessel Inspections to Meet Code Requirements for Two ISI Intervals Project stage: Request ML19196A0642019-08-23023 August 2019 Relied Request ISIR-4-10 Regarding Fourth Inservice Inspection Program Interval Project stage: Other 2019-05-30 |
| ML19196A064 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 08/23/2019 |
| From: | Lisa Regner Plant Licensing Branch III |
| To: | Gebbie J Indiana Michigan Power Co |
| Kuntz R, NRR/DORL/LPLIII, 415-3733 | |
| References | |
| EPID L-2019-LLR-0054 | |
| Download: ML19196A064 (7) | |
Similar Documents at Cook | |
|---|---|
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 MONTHYEARIR 05000315/20230042024-01-31031 January 2024
[Table view]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 Category:Safety Evaluation 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 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 |
Text
Code of Federal Regulations
/RA by Michael Ortenak for/
Code of Federal Regulations
Retrieved from "https://kanterella.com/w/index.php?title=ML19196A064&oldid=1885166"