ML14133A016
From kanterella
Jump to navigation
Jump to search
| ML14133A016 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 05/13/2014 |
| From: | Cuthbert D Alliance For A Clean Environment |
| To: | Macfarlane A NRC/Chairman, NRC Region 1 |
| BOWER, FL | |
| References | |
| Download: ML14133A016 (15) | |
Similar Documents at Limerick | |
|---|---|
Category:Report
MONTHYEARML24026A2962024-01-26026 January 2024
[Table view]Supplement to License Amendment Request to Revise the Licensing and Design Basis to Incorporate the Replacement of Existing Safety-Related Analog Control Systems with a Single Digital Plant Protection System (PPS)- Syrs, . LG-23-059, Owner'S Activity Report (OAR-1) for Li2R 172023-08-10010 August 2023 Owner'S Activity Report (OAR-1) for Li2R 17 ML23177A2242023-06-26026 June 2023 Supplement to License Amendment Request to Revise the Licensing and Design Basis to Incorporate the Replacement of Existing Safety-Related Analog Control Systems with a Single Digital Plant Protection . LG-22-101, Annual Commitment Change Summary Report2022-11-14014 November 2022 Annual Commitment Change Summary Report ML22224A1492022-08-15015 August 2022 Review of Limerick Generating Station Defense in Depth and Diversity Common Cause Failure Coping Analysis, WNA-AR-01074-GLIM-P, Revision 2, July 2022, and the Licensing Technical Report for the Limerick Generating Station Units 1&2 Digital NMP1L3469, Constellation Energy Company, LLC, Request for Use of Honeywell Mururoa V4F1 R Supplied Air Suits2022-06-30030 June 2022 Constellation Energy Company, LLC, Request for Use of Honeywell Mururoa V4F1 R Supplied Air Suits ML22046A0742022-02-14014 February 2022 Review of Limerick Generating Station Defense in Depth and Diversity Common Cause Failure Coping Analysis, WNA-AR-01074-GLIM-P, Rev 1. Without Attachment 3 Enclosure ML21070A4122021-03-11011 March 2021 Requesting Revision to License Condition in Appendix C in Renewed Facility Operating License ML21083A1712021-02-28028 February 2021 Attachment 3: Limerick Generating Station, Unit 2, 006N3997NP, Revision 1, High Burnup Lead Use Assembly (Hblua) Information Report February 2021 RS-21-001, Revised Proposed Alternative to Utilize Code Cases N-878 and N-880 for Carbon Steel Piping2021-01-0404 January 2021 Revised Proposed Alternative to Utilize Code Cases N-878 and N-880 for Carbon Steel Piping LG-20-105, Annual Commitment Change Summary Report2020-11-23023 November 2020 Annual Commitment Change Summary Report ML20303A1752020-10-23023 October 2020 Proposed Relief Request from Section XI Repair/Replacement Documentation for Bolting Replacement of Pressure Retaining Bolting ML20106E8282020-04-15015 April 2020 Submittal of Analytical Evaluation of Core Spray Injection Nozzle-to-Safe End Weld (N5A) ML19228A0232019-08-15015 August 2019 Proposed Alternative to Utilize Code Case N-879 RS-18-051, Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events2018-06-0707 June 2018 Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events ML18129A3342018-05-0404 May 2018 Corrosion Evaluation of the Limerick Unit 2 N-160 Reactor Vessel Nozzle Modification, Framatome Document No. 51-9271770-002 (Non-Proprietary) ML17255A0302017-09-12012 September 2017 Independent Spent Fuel Storage Installation, Registration of Use of Casks to Store Spent Fuel ML17152A3052017-06-0101 June 2017 N-16D Nozzle Repair - Submittal of Analytical Flaw Evaluation, Design Analysis, and Corrosion Evaluation (Rev. 1) ML17137A0682017-05-16016 May 2017 Proposed Relief Request Associated with Reactor Pressure Vessel Nozzle Repairs ML17131A1802017-05-11011 May 2017 Issuance of the Core Operating Limits Report (COLR) for Reload 14, Cycle 15 RS-16-177, High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from The..2016-11-28028 November 2016 High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from The.. ML16309A0172016-11-0404 November 2016 10 CFR 50.59 and 1 O CFR 72.48 Evaluation 24-Month Summary Report for the Period July 1, 2014 Through June 30, 2016 ML16307A0202016-11-0202 November 2016 Special Report - Accident Monitoring Instrumentation Inoperability RS-14-277, Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 12014-09-24024 September 2014 Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 1 ML14199A4112014-07-18018 July 2014 Special Report - Seismic Monitoring Instrumentation Inoperability ML14148A2802014-06-17017 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 ML14133A0222014-05-13013 May 2014 ACE Document Received at LIM Aam May 7, 2014 ML14133A0162014-05-13013 May 2014 ACE Attachment to NRC Chairman Macfarlane Letter of 3-31-14 ML14058B1562014-04-14014 April 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 ML14058B1202014-04-14014 April 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 ML13357A3312014-01-0606 January 2014 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Limerick Generating Station, Units 1 and 2, TAC Nos.: MF0847 and MF0848 RS-13-138, Updated Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the Limerick Generating Station, Unit 2, Report No. RS-13-1382013-10-0707 October 2013 Updated Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the Limerick Generating Station, Unit 2, Report No. RS-13-138 ML13284A1112013-10-0707 October 2013 Appendix AD - Area Walk-by Checklists (Awcs) ML13143A2562013-05-16016 May 2013 NRC Reply to ACE Questions Received March 21 and 27, 2013 RS-13-084, Response to March 12, 2012, Request for Information Per 10 CFR 50.45.(f) Recommendations of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, Enclosure 5, Recommendation 9.3, Emergency..2013-04-30030 April 2013 Response to March 12, 2012, Request for Information Per 10 CFR 50.45.(f) Recommendations of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, Enclosure 5, Recommendation 9.3, Emergency.. IR 05000456/20132022013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000272/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee ML13008A2192013-01-31031 January 2013 U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000454/20132022013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000461/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000237/20132022013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000373/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000352/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000219/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000277/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000254/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000289/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee RS-12-172, Company, Llc'S 180-day Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2012-11-19019 November 2012 Company, Llc'S 180-day Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident ML12342A1162012-11-0606 November 2012 MPR-3796, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Revision 1, Part 11 of 12 ML12342A1152012-11-0606 November 2012 MPR-3796, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Revision 1, Part 10 of 12 2024-01-26 Category:Technical MONTHYEARML24026A2962024-01-26026 January 2024
[Table view]Supplement to License Amendment Request to Revise the Licensing and Design Basis to Incorporate the Replacement of Existing Safety-Related Analog Control Systems with a Single Digital Plant Protection System (PPS)- Syrs, . ML23177A2242023-06-26026 June 2023 Supplement to License Amendment Request to Revise the Licensing and Design Basis to Incorporate the Replacement of Existing Safety-Related Analog Control Systems with a Single Digital Plant Protection . ML22224A1492022-08-15015 August 2022 Review of Limerick Generating Station Defense in Depth and Diversity Common Cause Failure Coping Analysis, WNA-AR-01074-GLIM-P, Revision 2, July 2022, and the Licensing Technical Report for the Limerick Generating Station Units 1&2 Digital NMP1L3469, Constellation Energy Company, LLC, Request for Use of Honeywell Mururoa V4F1 R Supplied Air Suits2022-06-30030 June 2022 Constellation Energy Company, LLC, Request for Use of Honeywell Mururoa V4F1 R Supplied Air Suits ML22046A0742022-02-14014 February 2022 Review of Limerick Generating Station Defense in Depth and Diversity Common Cause Failure Coping Analysis, WNA-AR-01074-GLIM-P, Rev 1. Without Attachment 3 Enclosure ML21070A4122021-03-11011 March 2021 Requesting Revision to License Condition in Appendix C in Renewed Facility Operating License RS-21-001, Revised Proposed Alternative to Utilize Code Cases N-878 and N-880 for Carbon Steel Piping2021-01-0404 January 2021 Revised Proposed Alternative to Utilize Code Cases N-878 and N-880 for Carbon Steel Piping ML20106E8282020-04-15015 April 2020 Submittal of Analytical Evaluation of Core Spray Injection Nozzle-to-Safe End Weld (N5A) ML19228A0232019-08-15015 August 2019 Proposed Alternative to Utilize Code Case N-879 RS-18-051, Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events2018-06-0707 June 2018 Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events ML18129A3342018-05-0404 May 2018 Corrosion Evaluation of the Limerick Unit 2 N-160 Reactor Vessel Nozzle Modification, Framatome Document No. 51-9271770-002 (Non-Proprietary) ML17152A3052017-06-0101 June 2017 N-16D Nozzle Repair - Submittal of Analytical Flaw Evaluation, Design Analysis, and Corrosion Evaluation (Rev. 1) ML17137A0682017-05-16016 May 2017 Proposed Relief Request Associated with Reactor Pressure Vessel Nozzle Repairs RS-16-177, High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from The..2016-11-28028 November 2016 High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from The.. RS-14-277, Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 12014-09-24024 September 2014 Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 1 ML14133A0162014-05-13013 May 2014 ACE Attachment to NRC Chairman Macfarlane Letter of 3-31-14 ML13357A3312014-01-0606 January 2014 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Limerick Generating Station, Units 1 and 2, TAC Nos.: MF0847 and MF0848 ML11255A1912011-09-0202 September 2011 Voluntary Special Report - Seismic Monitoring Instrumentation Actuation ML1024402642010-08-31031 August 2010 0000-0114-0580-RO-NP, Rev. 0, Limerick Generating Station, Units 1 & 2, Upper Shelf Energy Evaluation for LPCI Nozzle Forging Material ML1008504032010-03-31031 March 2010 NEDO-33484, Rev. 0, Safety Analysis Report for Limerick Generating Station Units 1 & 2 Thermal Power Optimization ML1008503982010-03-25025 March 2010 Markup of Proposed Technical Requirements Manual & Technical Specifications Bases Pages ML0912804312008-12-31031 December 2008 Annual Radioactive Effluent Release Report ML0821900132008-08-0707 August 2008 Monthly Operating Reports Second Quarter 2008 ML0912804322008-06-30030 June 2008 CY-LG-170-301, Revision 24, Offsite Dose Calculation Manual ML0808702442008-03-14014 March 2008 License Amendment Request, Revise LPRM Calibration Interval - Global Nuclear Fuel Report Limerick LPRM Calibration Interval Extension Support ML0808505652008-03-14014 March 2008 License Amendment Request - Revise LPRM Calibration Frequency, Supplemental Response - Global Nuclear Fuel Report - Limerick LPRM Calibration Interval Extension Support. ML0809906682008-03-0404 March 2008 License Amendment Request - Revised LPRM Calibration Frequency Supplemental Response - Global Nuclear Fuel Report - Gnf S-0000-0082-2744, Rev. 0, Limerick LPRM Calibration Interval Extension Support, (Non-Proprietary Version) ML0634601312006-12-0707 December 2006 Attachment 11, Exelon/Amergen Response to the Request for Additional Information, EP-EAL-0611, Criteria for Choosing Containment Radiation Monitor Reading Indicative Loss of the RCS Barrier ML0632502582006-11-16016 November 2006 Response to NRC Request for Additional Information Regarding TSTF-475, Revision 0, Control Rod Notch Testing Frequency and SRM Insert Control Rod Action, Dated March 21, 2005 ML0317703462003-06-17017 June 2003 Additional Information Regarding Notice of Proposed Amendments to Trust Agreement to Implement Assignment of Decommissioning Trust Funds for Exelon Generation Company, LLC ML17037B8851978-01-27027 January 1978 Letter Regarding a GE Report, Analytical Model for Estimating Drag Forces on Rigid Submerged Structures Caused by LOCA and Safety Relief Valve Ramshead Air Discharges, NEDO-21471, Dated September, 1977 ML17037B8881977-11-21021 November 1977 Letter Regarding Nedo 24070, Mark II Containment Supporting Program Report - Ramshead Safety/Relief Valve Load - Methodology Summary, September, 1977 ML17037B8911977-11-0303 November 1977 Letter Regarding Amendment 2, Supplement 2 (September 1977) to Mark II Containment Dynamic Forcing Functions Information Report (Dffr), NEDO-21061, Rev. 2 ML17037B8921977-10-25025 October 1977 Letter Regarding GE Topical Report Nedo 23617 Mark II Lead Plant Topical Report: Pool Boundary and Main Vent Chugging Load Justification, Dated July, 1977 ML17037B8941977-09-26026 September 1977 Letter Regarding GE Report Technical Basis for the Use of the Square Root of the Sum of Squares (Srss) Method for Combining Dynamic Loads on Mark II Plants - July, 1977 ML17037B8901977-09-23023 September 1977 Letter Regarding Mark II Containment Program Report, Comparison of the 1/3 Scale Mark II Containment Multivent Pool Swell Data with Analytical Methods, NEDO-21667, August 1977 ML17037B8951977-09-15015 September 1977 Letter Regarding Amendment 2, Supplement 1 (August 1977) to Mark II Containment Dynamic Forcing Functions Information Report (Dffr), NEDO-21061, Rev. 2 2024-01-26 |
Text
Retrieved from "https://kanterella.com/w/index.php?title=ML14133A016&oldid=1729788"