ML15182A067: Difference between revisions
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| number = ML15182A067 | | number = ML15182A067 | ||
| issue date = 07/20/2015 | | issue date = 07/20/2015 | ||
| title = McGuire, Units 1 & 2 - Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(F), Seismic Hazard Reevaluations | | title = McGuire, Units 1 & 2 - Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(F), Seismic Hazard Reevaluations for Recommendation 2.1 of the Near Term Task Force Review of Ins | ||
| author name = Vega F G | | author name = Vega F G | ||
| author affiliation = NRC/NRR/JLD/PMB | | author affiliation = NRC/NRR/JLD/PMB |
Revision as of 00:24, 2 March 2018
ML15182A067 | |
Person / Time | |
---|---|
Site: | McGuire, Mcguire |
Issue date: | 07/20/2015 |
From: | Vega F G Containment and Balance of Plant Branch |
To: | Capps S D Duke Energy Carolinas |
Vega, Frankie 415-1617 | |
References | |
TAC MF3689, TAC MF3690 | |
Download: ML15182A067 (20) | |
Category:Letter
MONTHYEARIR 05000369/20244022024-10-0808 October 2024
[Table view]Security Baseline Inspection Report 05000369/2024402 05000370/2024402 IR 05000369/20240052024-08-26026 August 2024 Updated Inspection Plan for McGuire Nuclear Station, Units 1 and 2, (Report 05000369-2024005 and 05000370-2024005) IR 05000369/20244042024-08-0101 August 2024 Cover Letter Security Baseline Inspection Report 05000369/2024404 and 05000370/2024404 IR 05000369/20253012024-07-29029 July 2024 Notification of Licensed Operator Initial Examination 05000369/2025301 and 05000370/2025301 IR 05000369/20244032024-07-25025 July 2024 – Cyber Security Inspection Report 05000369/2024403 and 05000370/2024403 Rev IR 05000369/20240022024-07-24024 July 2024 Integrated Inspection Report 05000369/2024002 and 05000370/2024002 ML24183A0972024-07-12012 July 2024 ISFSI; Catawba 1, 2 & ISFSI; McGuire 1, 2 & ISFSI; Oconee 1, 2, 3 & ISFSI; Shearon Harris 1; H. B. Robinson 2 & ISFSI; and Radioactive Package Shipping Under 10 CFR 71 (71-266 & 71-345) – Review of QA Program Changes EPID L-2024-LLQ-0002 IR 05000369/20244012024-07-0303 July 2024 – Security Baseline Inspection Report 05000369/2024401 and 05000370/2024401 ML24176A2802024-06-26026 June 2024 Notification of Target Set Inspection and Request for Information (NRC Inspection Report 05000369-2024404 and 05000370-2024404) IR 05000369/20240112024-06-0404 June 2024 Biennial Problem Identification and Resolution Inspection Report 05000369/2024011 and 05000370/2024011 ML24149A1772024-05-28028 May 2024 NRC Response to Duke Energy 2025 FOF Schedule Change Request (Catawba and McGuire) IR 05000369/20240012024-05-0808 May 2024 Integrated Inspection Report 05000369-2024001 and 05000370-2024001 and 07200038-2024001 ML24110A0382024-04-30030 April 2024 – Correction to Issuance of Amendment Nos. 330 and 309, Regarding Implementation of Technical Specifications Task Force (TSTF) Traveler TSTF 505, Revision 2, Provide Risk-Informed Extended Completion Times - Ritstf ML24100A8742024-04-10010 April 2024 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000369/2024403; and 05000370/2024403 ML24052A3062024-04-0808 April 2024 Issuance of Amendment Nos. 331 & 310, Regarding Adoption of Title 10 of Code of Federal Regulations Section 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Plants ML24031A5402024-03-26026 March 2024 Issuance of Amendment Nos. 330 and 309 Regarding Implementation of TSTF 505,Rev. 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4B ML24085A2402024-03-21021 March 2024 Requalification Program Inspection - McGuire Nuclear Station IR 05000369/20240102024-03-13013 March 2024 Comprehensive Engineering Team Inspection Report 05000369/2024010 and 05000370/2024010 IR 05000369/20230062024-02-28028 February 2024 Annual Assessment Letter for McGuire Nuclear Station, Units 1 and 2 - NRC Inspection Report 05000369/2023006 and 05000370/2023006 ML24024A2182024-02-0505 February 2024 Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting) IR 05000369/20230042024-01-31031 January 2024 Integrated Inspection Report 05000369/2023004 and 05000370/2023004 ML24019A1392024-01-25025 January 2024 TSTF 505 and 50.69 Audit Summary ML24019A2002024-01-24024 January 2024 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection IR 05000369/20234022023-12-14014 December 2023 – Material Control and Accounting Program Inspection Report 05000369/2023402 and 05000370/2023402 ML23317A2272023-11-17017 November 2023 William B. McGuire Nuclear Station, Units 1 and 2 - Transmittal of Dam Inspection Report - Non-Proprietary ML23317A3462023-11-14014 November 2023 Duke Fleet - Correction Letter to License Amendment Nos. 312 & 340 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000369/20230032023-10-24024 October 2023 Integrated Inspection Report 05000369/2023003 and 05000370/2023003; and Inspection Report 07200038/2023001 IR 05000369/20230102023-10-13013 October 2023 Age Related Degradation Inspection Report 05000369/2023010 and 05000370/2023010 ML23256A0882023-09-25025 September 2023 Issuance of Alternative to Steam Generator Welds IR 05000369/20233012023-09-20020 September 2023 William B. McGuire Nuclear Station - NRC Examination Report 05000369/2023301 and 05000370/2023301 ML23230A0652023-08-31031 August 2023 William B. McGuire Nuclear Station, Units 1 and 2 - Relief Request Use of Later Edition of ASME Code ML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000369/20230052023-08-25025 August 2023 Updated Inspection Plan for McGuire Nuclear Station Units 1 and 2 (Report 05000369/2023005 and 05000370/2023005) IR 05000369/20230022023-07-28028 July 2023 Integrated Inspection Report 05000369/2023002 and 05000370/2023002 IR 05000369/20234202023-07-24024 July 2023 Security Baseline Inspection Report 050003692023420 and 050003702023420 ML23206A0092023-07-24024 July 2023 William B. McGuire Nuclear Station Operator Licensing Written Examination Approval 05000369/2023301 and 05000370/2023301 ML23207A0762023-07-14014 July 2023 EN 56557 - Update to Part 21 Report Re Potential Defect with Trane External Auto/Stop Emergency Stop Relay Card Pn: XI2650728-06 ML23159A2712023-06-20020 June 2023 William B. McGuire Nuclear Station, Unit 1 - Relief Request Impractical Reactor System Welds ML23237A2672023-06-13013 June 2023 June 13, 2002 - Meeting Announcement - McGuire and Catawba Nuclear Stations 50-369, 50-370 and 50-413, 50-414 ML23159A0052023-06-0505 June 2023 56557-EN 56557 - Paragon - Redlined ML23115A2122023-05-0101 May 2023 Review of the Spring 2022 Steam Generator Tube Inspection Report ML23118A0762023-05-0101 May 2023 Approval for Use of Specific Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI IR 05000369/20230012023-05-0101 May 2023 Integrated Inspection Report 05000369/2023001 and 05000370/2023001 ML23094A1832023-04-18018 April 2023 Audit Plan TSTF-505, Rev. 2, RITSTF Initiative 4B & 10 CFR 50.69, Risk-Informed Categorization & Treatment of Structures, Systems & Components for Nuclear Power Reactors (EPIDs L-2023-LLA-0021 & L-2023-LLA-0022) ML22332A4932023-03-10010 March 2023 William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility IR 05000369/20220062023-03-0101 March 2023 Annual Assessment Letter for McGuire Nuclear Station Units 1 and 2 (NRC Inspection Report 05000369/2022006 and 05000370 2022006) IR 05000369/20220042023-01-30030 January 2023 Mcguire Nuclear Station - Integrated Inspection Report 05000369/2022004 and 05000370/2022004 IR 05000369/20224202023-01-11011 January 2023 Security Baseline Inspection Report 05000369/2022420 and 05000370/2022420 ML22356A0512022-12-14014 December 2022 Curtiss-Wright Nuclear Division, Letter Regarding Potential Efect in a Configuration of the 11/2 Inch Quick Disconnect Connector Cable Assemblies Supplied to Duke Energy (See Attached Spreadsheet) for a Total of 460 of Connectors Only Suppl ML22347A1512022-12-13013 December 2022 William B. Mcguire Nuclear Station Notification of Licensed Operator Initial Examination 05000369/2023301 and 05000370/2023301 2024-08-26 Category:Report MONTHYEARRA-24-0185, Snubber Program Plan - Snubber Program Plan Revision, AD-EG-MNS-16182024-08-28028 August 2024
[Table view]Snubber Program Plan - Snubber Program Plan Revision, AD-EG-MNS-1618 ML24047A2092024-02-22022 February 2024 Calendar Year 2023 Baseline Inspection Completion RA-19-0245, of DPC-NE-1007-P, Conditional Exemption of the EOC Mtc Measurement Methodology2021-10-25025 October 2021 of DPC-NE-1007-P, Conditional Exemption of the EOC Mtc Measurement Methodology RA-20-0363, Post Accident Monitoring Report 369-2020-012020-12-0101 December 2020 Post Accident Monitoring Report 369-2020-01 RA-19-0223, Annual Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models Pursuant to 10CFR 50.462019-05-30030 May 2019 Annual Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models Pursuant to 10CFR 50.46 ML19058A4162019-03-0808 March 2019 Staff Evaluation Related to Reactor Vessel Internals Inspection Plan Based on MRP-227-A ML18135A0722018-04-30030 April 2018 ANP-3658, Revision 0, Evaluation of the McGuire Units 1 and 2 Upflow Modification for 60 Years. MNS-17-050, Review Request for the Aging Management Program and Inspection Plan for the Reactor Vessel Internals to Implement MRP-227-A2017-12-13013 December 2017 Review Request for the Aging Management Program and Inspection Plan for the Reactor Vessel Internals to Implement MRP-227-A ML17171A2772017-06-12012 June 2017 Selected Licensee Commitments List of Revised Effected Sections ML16363A3542016-12-0909 December 2016 54003-CALC-01, Evaluation of Risk Significance of Permanent ILRT Extension. ML16293A6662016-10-31031 October 2016 Staff Assessment of Response to 10 CFR 50.54(f) Information Request - Flood Causing Mechanism Reevaluation (CAC Nos. MF3623 and MF3624) ML16294A2532016-10-12012 October 2016 Issue MNS Technical Specification 5.6 Rev. 2 Amend. 288/267 ML16237A3542016-08-31031 August 2016 Staff Review of Spent Fuel Pool Evaluation Associated with Reevaluated Seismic Hazard Implementing Near-Term Task Force Recommendation 2.1 MNS-16-008, Expedited Seismic Evaluation Process (ESEP) Closeout, Response to NRC Request for Information, Per 10 CFR 50.54(f) Regarding Recommendations 2.1 of the Near-Term Task Force Review of Insights from the Fukushima..2016-02-0404 February 2016 Expedited Seismic Evaluation Process (ESEP) Closeout, Response to NRC Request for Information, Per 10 CFR 50.54(f) Regarding Recommendations 2.1 of the Near-Term Task Force Review of Insights from the Fukushima.. ML15313A1642015-10-0808 October 2015 Submittal of 10 CFR 71.95 Report on the 8-120B Cask MNS-15-072, Selected Licensee Commitment Special Report 2015-01, Nuclear Condition Report No. 1943414, Standby Shutdown System Was Non-functional for a Period Greater than 7 Days2015-09-10010 September 2015 Selected Licensee Commitment Special Report 2015-01, Nuclear Condition Report No. 1943414, Standby Shutdown System Was Non-functional for a Period Greater than 7 Days ML15246A1452015-08-11011 August 2015 Submittal of 10 CFR 71.95 Report on the 8-120B Cask ML15219A5662015-07-29029 July 2015 MNS-TS-5,6 - Distribution to Manual Holders - Amendment 278/258 ML15182A0672015-07-20020 July 2015 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(F), Seismic Hazard Reevaluations for Recommendation 2.1 of the Near Term Task Force Review of Insights From.. ML15141A0532015-03-0303 March 2015 Enclosure 5, Revision 0 to EP-EALCALC-MNS-1401, MNS Radiological Effluent EAL Values. MNS-15-014, LTR-PAFM-14-114-NP, Rev. 0, Technical Justification to Support Extended Volumetric Examination Interval for McGuire, Unit 1, Reactor Vessel Inlet Nozzle to Safe End Dissimilar Metal Welds (Non-Proprietary)2015-02-28028 February 2015 LTR-PAFM-14-114-NP, Rev. 0, Technical Justification to Support Extended Volumetric Examination Interval for McGuire, Unit 1, Reactor Vessel Inlet Nozzle to Safe End Dissimilar Metal Welds (Non-Proprietary) MNS-15-004, Annual Commitment Change Report2015-01-29029 January 2015 Annual Commitment Change Report MNS-14-097, Expedited Seismic Evaluation Process Report (CEUS Sites), Response to NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1 of the Near-Term Task Force Review.2014-12-17017 December 2014 Expedited Seismic Evaluation Process Report (CEUS Sites), Response to NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1 of the Near-Term Task Force Review. ML14156A2872014-06-10010 June 2014 Staff Assessment of the Flooding Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-ichi Nuclear Power Plant Accident ML14114A3052014-05-0808 May 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-ichi Nuclear Power Plant Accident ML14085A0652014-04-24024 April 2014 NRC Staff Review of the Documentation Provided by Duke Energy Carolinas, LLC, for McGuire Concerning Resolution of Generic LTR 2004-02 Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressuriz MNS-14-029, Seismic Hazard and Screening Report (CEUS Sites), Response to NRC 10 CFR 50.54(f) Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3 and 9.3 of The.2014-03-20020 March 2014 Seismic Hazard and Screening Report (CEUS Sites), Response to NRC 10 CFR 50.54(f) Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3 and 9.3 of The. MNS-14-030, Annual Commitment Change Report2014-03-19019 March 2014 Annual Commitment Change Report ML13338A4062014-01-16016 January 2014 William B. McGuire Nuclear Station, Units 1 and 2 - Interim Staff Evaluation and Audit Report Relating to Overall Integrated Plan in Response to Order EA-12-049 - Mitigation Strategies ML13357A3502014-01-10010 January 2014 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for McGuire Nuclear Station, Units 1 and 2, TAC Nos.: MF1160 and MF1161 CNS-13-005, License Amendment Request for Methodology Report DPC-NE-3001-P, Revision 1, Multidimensional Reactor Transients and Safety Analysis Physics Parameters Methodology2013-11-14014 November 2013 License Amendment Request for Methodology Report DPC-NE-3001-P, Revision 1, Multidimensional Reactor Transients and Safety Analysis Physics Parameters Methodology ML13338A5772013-09-30030 September 2013 Oig Semiannual Report to Congress - Fall 2013 ML13276A1272013-09-26026 September 2013 Transition to 10 CFR 50.48(c)- NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants, 2001 Edition. Cover Through Attachment B ML13276A1282013-09-26026 September 2013 Transition to 10 CFR 50.48(c)- NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants, 2001 Edition. Attachment B Through End ML13190A2742013-05-14014 May 2013 Attachment 8, Supplemental Peer Review Summary Reports for Initially Inaccessible Components ML13142A0122013-03-25025 March 2013 Annual Commitment Change Report ML13190A2732012-11-15015 November 2012 Attachment 6, NTTF 2.3 Seismic Peer Review Report ML13003A3402012-11-15015 November 2012 Document 1457690101-R-M-00003, Rev. 0, NTTF 2.3 Seismic Peer Review Report, Attachment 6, Unit 1 ML12151A4142012-05-16016 May 2012 Selected Licensee Commitments (SLC) Loes ML12153A3292012-03-31031 March 2012 Attachment 6 - Duke Energy Methodology Report DPC-NE-1007, Revision 0, Conditional Exemption of the EOC Mtc Measurement Methodology (Non-proprietary) NEI 99-04, McGuire Nuclear Station, Units 1 and 2 - Annual Commitment Change Report2012-03-29029 March 2012 McGuire Nuclear Station, Units 1 and 2 - Annual Commitment Change Report ML11279A0352011-09-21021 September 2011 Relief Request Serial # 11-MN-001, Limited Weld Examinations for Refueling Outages 1EOC20 and 2EOC19 ML11102A1312011-04-0505 April 2011 Summary Report of Evaluations Performed Pursuant to 10 CFR 50.59 Changes, Tests and Experiments ML1023001682010-08-16016 August 2010 Units 1 & 2 - Supplement 2 to License Amendment Request for Duke Energy Cyber Security Plan ML1019304172010-05-0606 May 2010 Tritium Database Report ML1010301792010-03-31031 March 2010 Annual Commitment Change Report NEI 99-04, McGuire, Units 1 & 2 - Annual Commitment Change Report2010-03-31031 March 2010 McGuire, Units 1 & 2 - Annual Commitment Change Report ML0908202662009-03-16016 March 2009 Submittal of Facility Operating License Revision ML0904007952009-02-0404 February 2009 GSI-189 Action Plan, Feb. 09 Update, Publicly Available Version ML0833701812008-11-0606 November 2008 Independent Spent Fuel Storage Installation (ISFSI) - 10 CFR 72.48 Summary Report 2024-08-28 Category:Miscellaneous MONTHYEARML24047A2092024-02-22022 February 2024
[Table view]Calendar Year 2023 Baseline Inspection Completion RA-19-0223, Annual Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models Pursuant to 10CFR 50.462019-05-30030 May 2019 Annual Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models Pursuant to 10CFR 50.46 ML19058A4162019-03-0808 March 2019 Staff Evaluation Related to Reactor Vessel Internals Inspection Plan Based on MRP-227-A MNS-17-050, Review Request for the Aging Management Program and Inspection Plan for the Reactor Vessel Internals to Implement MRP-227-A2017-12-13013 December 2017 Review Request for the Aging Management Program and Inspection Plan for the Reactor Vessel Internals to Implement MRP-227-A ML17171A2772017-06-12012 June 2017 Selected Licensee Commitments List of Revised Effected Sections ML16293A6662016-10-31031 October 2016 Staff Assessment of Response to 10 CFR 50.54(f) Information Request - Flood Causing Mechanism Reevaluation (CAC Nos. MF3623 and MF3624) ML16294A2532016-10-12012 October 2016 Issue MNS Technical Specification 5.6 Rev. 2 Amend. 288/267 ML16237A3542016-08-31031 August 2016 Staff Review of Spent Fuel Pool Evaluation Associated with Reevaluated Seismic Hazard Implementing Near-Term Task Force Recommendation 2.1 ML15313A1642015-10-0808 October 2015 Submittal of 10 CFR 71.95 Report on the 8-120B Cask MNS-15-072, Selected Licensee Commitment Special Report 2015-01, Nuclear Condition Report No. 1943414, Standby Shutdown System Was Non-functional for a Period Greater than 7 Days2015-09-10010 September 2015 Selected Licensee Commitment Special Report 2015-01, Nuclear Condition Report No. 1943414, Standby Shutdown System Was Non-functional for a Period Greater than 7 Days ML15246A1452015-08-11011 August 2015 Submittal of 10 CFR 71.95 Report on the 8-120B Cask ML15182A0672015-07-20020 July 2015 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(F), Seismic Hazard Reevaluations for Recommendation 2.1 of the Near Term Task Force Review of Insights From.. ML15141A0532015-03-0303 March 2015 Enclosure 5, Revision 0 to EP-EALCALC-MNS-1401, MNS Radiological Effluent EAL Values. MNS-15-004, Annual Commitment Change Report2015-01-29029 January 2015 Annual Commitment Change Report ML14156A2872014-06-10010 June 2014 Staff Assessment of the Flooding Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-ichi Nuclear Power Plant Accident ML14114A3052014-05-0808 May 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-ichi Nuclear Power Plant Accident ML14085A0652014-04-24024 April 2014 NRC Staff Review of the Documentation Provided by Duke Energy Carolinas, LLC, for McGuire Concerning Resolution of Generic LTR 2004-02 Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressuriz MNS-14-029, Seismic Hazard and Screening Report (CEUS Sites), Response to NRC 10 CFR 50.54(f) Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3 and 9.3 of The.2014-03-20020 March 2014 Seismic Hazard and Screening Report (CEUS Sites), Response to NRC 10 CFR 50.54(f) Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3 and 9.3 of The. MNS-14-030, Annual Commitment Change Report2014-03-19019 March 2014 Annual Commitment Change Report ML13338A5772013-09-30030 September 2013 Oig Semiannual Report to Congress - Fall 2013 ML13142A0122013-03-25025 March 2013 Annual Commitment Change Report ML12151A4142012-05-16016 May 2012 Selected Licensee Commitments (SLC) Loes NEI 99-04, McGuire Nuclear Station, Units 1 and 2 - Annual Commitment Change Report2012-03-29029 March 2012 McGuire Nuclear Station, Units 1 and 2 - Annual Commitment Change Report ML11279A0352011-09-21021 September 2011 Relief Request Serial # 11-MN-001, Limited Weld Examinations for Refueling Outages 1EOC20 and 2EOC19 ML11102A1312011-04-0505 April 2011 Summary Report of Evaluations Performed Pursuant to 10 CFR 50.59 Changes, Tests and Experiments ML1023001682010-08-16016 August 2010 Units 1 & 2 - Supplement 2 to License Amendment Request for Duke Energy Cyber Security Plan ML1019304172010-05-0606 May 2010 Tritium Database Report ML1010301792010-03-31031 March 2010 Annual Commitment Change Report NEI 99-04, McGuire, Units 1 & 2 - Annual Commitment Change Report2010-03-31031 March 2010 McGuire, Units 1 & 2 - Annual Commitment Change Report ML0908202662009-03-16016 March 2009 Submittal of Facility Operating License Revision ML0833701812008-11-0606 November 2008 Independent Spent Fuel Storage Installation (ISFSI) - 10 CFR 72.48 Summary Report ML0809305052008-03-20020 March 2008 License Amendment Request for Full Scope Implementation of the Alternative Source Term ML0807301312008-02-28028 February 2008 Response to Request for Additional Information on GL-04-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors ML0731000852007-11-0101 November 2007 Transmittal of DPC-NE-2012-A, Dynamic Rod Worth Measurement Using Casmo/Simulate ML0708005462007-03-13013 March 2007 Report Pursuant to 10 CFR 50.46, Changes to or Errors in an ECCS Evaluation Model ML0706504222007-02-27027 February 2007 Fitness-For-Duty Program Performance Data Reports for Period July 1, 2006 Through December 31, 2006 ML0624904272006-08-28028 August 2006 Fitness-For Duty Program Performance Data Reports for Period Covering January 1, 2006 Through June 30, 2006 ML0606601682006-02-21021 February 2006 Fitness-For-Duty Program Performance Data Reports ML0528503312005-09-28028 September 2005 Core Operating Limits Report (COLR) ML0524402932005-08-24024 August 2005 Fitness-For-Duty Program Performance Data Reports ML0517902102005-06-21021 June 2005 Report Pursuant to 10 CFR 50.46, Changes to or Errors in an ECCS Evaluation Model ML0506100302005-02-18018 February 2005 Duke Energy Corporation, Fitness-For-Duty Program Performance Data Reports for Period Covering 07/01/2004 Through 12/31/2004 ML0424505372004-08-20020 August 2004 Letter Transmitting Fitness-For-Duty Program Performance Data Reports for Duke Energy Corp Oconee, McGuire and Catawba Nuclear Stations and the General Office ML0324715282003-08-22022 August 2003 Fitness-for-Duty Program Performance Data Reports ML0312100492003-04-24024 April 2003 Duke Energy Topical Report Response to Request for Additional Information Letter Dated April 4, 2003 ML0310504592003-04-0303 April 2003 Submittal of Summary Report of Evaluations Performed at McGuire Nuclear Station ML0306306812003-02-25025 February 2003 Fitness-for-Duty Program, Performance Data Reports ML0226600412002-09-12012 September 2002 Response to Request for Additional Information - Topical Report DPC-NE-1005P, Revision 0, Nuclear Design Methodology Using CASMO/4SIMULATE-3 MOX (Proprietary) ML0234503982002-08-0101 August 2002 Part 2 of 2, McGuire ASME Inservice Testing Program Revision 26 ML0234503402002-08-0101 August 2002 Part 1 of 2, McGuire ASME Inservice Testing Program Revision 26 2024-02-22 |
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