ML063620266
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| ML063620266 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 12/21/2006 |
| From: | AmerGen Energy Co |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| U-603798 363975 | |
| Download: ML063620266 (83) | |
Similar Documents at Clinton | |
|---|---|
Category:Report
MONTHYEARRS-23-073, Request for Partial Site Release2023-06-0707 June 2023
[Table view]Request for Partial Site Release 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 ML22014A0052022-01-13013 January 2022 COVID-19 Related Request for Exemption from Part 26 Work Hours Requirements RS-21-005, Request for License Amendment to Revise Degraded Voltage Relay Allowable Values2021-01-20020 January 2021 Request for License Amendment to Revise Degraded Voltage Relay Allowable Values 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 ML20303A1752020-10-23023 October 2020 Proposed Relief Request from Section XI Repair/Replacement Documentation for Bolting Replacement of Pressure Retaining Bolting U-604712, Submittal of the Snubber Program Plan for the Fourth 10-Year Interval2020-06-24024 June 2020 Submittal of the Snubber Program Plan for the Fourth 10-Year Interval ML19228A0232019-08-15015 August 2019 Proposed Alternative to Utilize Code Case N-879 ML18360A4722018-12-14014 December 2018 Attachment 4: Training Material on Diesel Generator Malfunctions ML18360A4712018-12-14014 December 2018 Attachment 3: EC 626319, Battery Coping Time Evaluation to Support Inadvertent Isolation of Div. II Air Start Receiver Valves ML18360A4692018-12-14014 December 2018 Attachment 1: Summary of Exelon Position ML18360A4702018-12-14014 December 2018 Attachment 2: Response to NRC Questions and Documentation Requests ML18360A4852018-12-14014 December 2018 Attachment 17: Inconsistencies Between FLEX SE and Choice Letter Assumptions ML18360A4842018-12-14014 December 2018 Attachment 16: Graph of RPV Water Level ML18360A4832018-12-14014 December 2018 Attachment 15: FLEX and Cross-tie Training Material ML18360A4732018-12-14014 December 2018 Attachment 5: Senior Reactor Operator Surveys ML18360A4742018-12-14014 December 2018 Attachment 6: CPS Shift Manager Surveys Regarding ELAP Scenarios ML18360A4752018-12-14014 December 2018 Attachment 7: Time Validation - Performance of SBO and Starting of Division 2 Diesel Generator ML18360A4822018-12-14014 December 2018 Attachment 14: CPS Procedure 4200.01 C002, DC Load Shedding During a 580, Rev 5a ML18360A4812018-12-14014 December 2018 Attachment 13: Simulator Exercise Guide SE-JIT-42, Loss of AC, Loss of SDC and Lowering RPV Level, Rev 1 ML18360A4802018-12-14014 December 2018 Attachment 12: Time Validation - Performance of Division 3 DG to Division 2 Bus Cross-tie ML18360A4792018-12-14014 December 2018 Attachment 11: Procedures and Training Material on Maintaining RPV Pressure Low ML18360A4782018-12-14014 December 2018 Attachment 10: HEP Evaluation Related to Shutdown Cooling Isolation ML18360A4772018-12-14014 December 2018 Attachment 9: Procedures on Shutdown Cooling Isolation ML18360A4762018-12-14014 December 2018 Attachment 8: 2017 Training Material on Diesel Generator Air Start Flow Plow RS-15-320, Revised Final Integrated Plan Document - Mitigating Strategies NRC Order, EA-12-0492015-12-14014 December 2015 Revised Final Integrated Plan Document - Mitigating Strategies NRC Order, EA-12-049 RS-15-269, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors2015-10-23023 October 2015 Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors ML15062A1152014-12-22022 December 2014 International Atomic Energy Agency (Iaea), Operational Safety Review Team (Osart) Mission to Clinton Report - 11- 28 August 2014 RS-14-312, Supplemental Response to Request for Additional Information Regarding Fukushima Lessons Learned - Flood Hazard Reevaluation Report2014-11-0303 November 2014 Supplemental Response to Request for Additional Information Regarding Fukushima Lessons Learned - Flood Hazard Reevaluation Report 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 ML14164A2982014-06-26026 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 ML14176A9612014-06-24024 June 2014 Submittal of Non-Proprietary BWROG Technical Product, BWROGTP-11-006 - ECCS Containment Walkdown Procedure, Rev 1 (January 2011), as Formally Requested During the Public Meeting Held on April 30, 2014 RS-14-112, Reports Associated with Results of Post-Irradiation Examination (Pie) of Global Nuclear Fuel (Gnf) GE14i Isotope Test Assembly (ITA)2014-03-27027 March 2014 Reports Associated with Results of Post-Irradiation Examination (Pie) of Global Nuclear Fuel (Gnf) GE14i Isotope Test Assembly (ITA) ML13338A6562013-12-0909 December 2013 Mega-Tech Services, LLC, Technical Evaluation Report Regarding the Overall Integrated Plan for Clinton Power Station, Unit 1, TAC No.: MF0901 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 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 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 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 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 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 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 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 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 ML12340A3492012-11-27027 November 2012 12Q0108.60-R-001, Rev. 0, Seismic Walkdown Checklists, C-1 Through C-143 RS-12-165, 12Q0108.60-R-001, Rev. 0, Seismic Walkdown Checklists, C-1 Through C-1432012-11-27027 November 2012 12Q0108.60-R-001, Rev. 0, Seismic Walkdown Checklists, C-1 Through C-143 RS-12-165, 12Q0108.60-R-001, Rev. 0, Seismic Walkdown Checklist, C-286 Through F-142012-10-30030 October 2012 12Q0108.60-R-001, Rev. 0, Seismic Walkdown Checklist, C-286 Through F-14 ML12340A3482012-10-30030 October 2012 12Q0108.60-R-001, Rev. 0, Seismic Walkdown Checklist, C-286 Through F-14 2023-06-07 Category:Technical MONTHYEARNMP1L3469, Constellation Energy Company, LLC, Request for Use of Honeywell Mururoa V4F1 R Supplied Air Suits2022-06-30030 June 2022
[Table view]Constellation Energy Company, LLC, Request for Use of Honeywell Mururoa V4F1 R Supplied Air Suits RS-21-005, Request for License Amendment to Revise Degraded Voltage Relay Allowable Values2021-01-20020 January 2021 Request for License Amendment to Revise Degraded Voltage Relay Allowable Values 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 U-604712, Submittal of the Snubber Program Plan for the Fourth 10-Year Interval2020-06-24024 June 2020 Submittal of the Snubber Program Plan for the Fourth 10-Year Interval ML19228A0232019-08-15015 August 2019 Proposed Alternative to Utilize Code Case N-879 RS-15-320, Revised Final Integrated Plan Document - Mitigating Strategies NRC Order, EA-12-0492015-12-14014 December 2015 Revised Final Integrated Plan Document - Mitigating Strategies NRC Order, EA-12-049 RS-14-312, Supplemental Response to Request for Additional Information Regarding Fukushima Lessons Learned - Flood Hazard Reevaluation Report2014-11-0303 November 2014 Supplemental Response to Request for Additional Information Regarding Fukushima Lessons Learned - Flood Hazard Reevaluation Report 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 ML14176A9612014-06-24024 June 2014 Submittal of Non-Proprietary BWROG Technical Product, BWROGTP-11-006 - ECCS Containment Walkdown Procedure, Rev 1 (January 2011), as Formally Requested During the Public Meeting Held on April 30, 2014 RS-14-112, Reports Associated with Results of Post-Irradiation Examination (Pie) of Global Nuclear Fuel (Gnf) GE14i Isotope Test Assembly (ITA)2014-03-27027 March 2014 Reports Associated with Results of Post-Irradiation Examination (Pie) of Global Nuclear Fuel (Gnf) GE14i Isotope Test Assembly (ITA) ML13338A6562013-12-0909 December 2013 Mega-Tech Services, LLC, Technical Evaluation Report Regarding the Overall Integrated Plan for Clinton Power Station, Unit 1, TAC No.: MF0901 ML12340A3492012-11-27027 November 2012 12Q0108.60-R-001, Rev. 0, Seismic Walkdown Checklists, C-1 Through C-143 RS-12-165, 12Q0108.60-R-001, Rev. 0, Seismic Walkdown Checklists, C-1 Through C-1432012-11-27027 November 2012 12Q0108.60-R-001, Rev. 0, Seismic Walkdown Checklists, C-1 Through C-143 RS-12-165, 12Q0108.60-R-001, Rev. 0, Seismic Walkdown Checklist, C-286 Through F-142012-10-30030 October 2012 12Q0108.60-R-001, Rev. 0, Seismic Walkdown Checklist, C-286 Through F-14 RS-12-165, 12Q0108.60-R-001, Rev. 0, Seismic Walkdown Report2012-10-30030 October 2012 12Q0108.60-R-001, Rev. 0, Seismic Walkdown Report ML12340A3482012-10-30030 October 2012 12Q0108.60-R-001, Rev. 0, Seismic Walkdown Checklist, C-286 Through F-14 ML12340A3472012-10-30030 October 2012 12Q0108.60-R-001, Rev. 0, Seismic Walkdown Report RS-12-165, 12Q0108.60-R-001, Rev. 0, Seismic Walkdown Checklist, C-144 Through C-2852012-10-0101 October 2012 12Q0108.60-R-001, Rev. 0, Seismic Walkdown Checklist, C-144 Through C-285 RS-12-082, Reports Associated with Results of Post-Irradiation Examination (Pie) of Global Nuclear Fuel (Gnf) GE14i Isotope Test Assembly (ITA)2012-05-14014 May 2012 Reports Associated with Results of Post-Irradiation Examination (Pie) of Global Nuclear Fuel (Gnf) GE14i Isotope Test Assembly (ITA) ML0904007952009-02-0404 February 2009 GSI-189 Action Plan, Feb. 09 Update, Publicly Available Version ML0821900132008-08-0707 August 2008 Monthly Operating Reports Second Quarter 2008 ML0636202642006-12-31031 December 2006 Hydraulic Model Study of High Pressure Core Spray Pump Suction to Evaluate the Formation of Air Drawing Vortices and Air Withdrawal ML0636202662006-12-21021 December 2006 Attachment 2, U-603798, Engineering Change Evaluation 363975 Revision 0 U-603798, Attachment 3, U-603798, SA-1578, Revision 3, Significance Determination Process (SDP) Evaluation for CPS HPCS RCIC Storage Tank Suction Vortexing2006-12-21021 December 2006 Attachment 3, U-603798, SA-1578, Revision 3, Significance Determination Process (SDP) Evaluation for CPS HPCS RCIC Storage Tank Suction Vortexing 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 ML0508202832005-03-31031 March 2005 GENE-0000-0023-6259-05NP, Rev 1, Amergen Energy Co, LLC Clinton Power Station BWRVIP-04A Core Shroud Repair Design Submittal to the Nuclear Regulatory Commission (Nrc). ML0508202932005-02-28028 February 2005 GENE-0000-0023-6259-03NP, Rev 2, Amergen Energy Co, LLC Clinton Power Station Non-Core Support Structural Components Assessment. ML0508202982005-02-28028 February 2005 GENE-0000-0023-6259-04NP, Rev 0, Amergen Energy Co., LLC Clinton Power Station Unit 1 Core Shroud Repair GE Input to IOCFR50.59 Evaluation by Cps. ML0423901812004-07-16016 July 2004 Holtec International Report No. HI-2033124 Spent Fuel Storage Expansion at Clinton Power Station. RS-04-024, Request for Amendment to Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles in Accordance with the Guidance of Generic Letter 91-042004-05-20020 May 2004 Request for Amendment to Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles in Accordance with the Guidance of Generic Letter 91-04 ML0412109162004-04-22022 April 2004 Technical Evaluation of Extending Division 1 and 2 Inverter Completion Time (CT) ML0802902312004-02-12012 February 2004 Westinghouse Technical Bulletin: Information Regarding Recent Crossflow Ultrasonic Flow Measurement System Performance Observations, TB-04-4 ML0327216212003-09-25025 September 2003 Site Safety Analysis Report for the Exelon Generation Company, LLC Early Site Permit, Appendix a, Chapter 6, Response of Soil and Rock to Dynamic and Static Loading ML0327216132003-09-25025 September 2003 Site Safety Analysis Report for the Exelon Generation Company, LLC Early Site Permit, Table of Contents, Appendix a, Attachment A-4, Stratigraphics Cone Penetrometer Test Report ML0327216152003-09-25025 September 2003 Site Safety Analysis Report for the Exelon Generation Company, LLC Early Site Permit, Appendix a, Attachment A-5, Geovision Suspension Logging Report ML0327216172003-09-25025 September 2003 Site Safety Analysis Report for the Exelon Generation Company, LLC Early Site Permit, Appendix a, Attachment A-6, TSC, Laboratory Test Results ML0327216192003-09-25025 September 2003 Site Safety Analysis Report for the Exelon Generation Company, LLC Early Site Permit, Appendix a, Attachment A-7, Results of Resonant Column/Cyclic Torsional Shear Testing ML0327216202003-09-25025 September 2003 Site Safety Analysis Report for the Exelon Generation Company, LLC Early Site Permit, Appendix a, Geotechnical Report, Table of Contents Through Figure 5-24 ML0327306082003-09-25025 September 2003 Site Safety Analysis Report for the Exelon Generation Company, LLC Early Site Permit, Appendix B, Seismic Hazards Report, Attachment 1, Table of Contents Through Figure B-1-6 ML0327306092003-09-25025 September 2003 Site Safety Analysis Report for the Exelon Generation Company, LLC Early Site Permit, Appendix B, Seismic Hazards Report, Attachment 1, Figures B-1-6 Through B-1-11 ML0327306102003-09-25025 September 2003 Site Safety Analysis Report for the Exelon Generation Company, LLC Early Site Permit, Appendix B, Seismic Hazards Report, Attachment 1, Figures B-1-12 Through Figure B-2-2 ML0327306122003-09-25025 September 2003 Site Safety Analysis Report for the Exelon Generation Company, LLC Early Site Permit, Appendix B, Seismic Hazards Report, Table of Contents Through Figure 2.1-19 ML0327306132003-09-25025 September 2003 Site Safety Analysis Report for the Exelon Generation Company, LLC Early Site Permit, Appendix B, Seismic Hazards Report, Figures 2.1-20 Through Plate 1 ML0327306142003-09-25025 September 2003 Site Safety Analysis Report for the Exelon Generation Company, LLC Early Site Permit, Table of Contents Through Figure 2.1-2 ML0327306152003-09-25025 September 2003 Site Safety Analysis Report for the Exelon Generation Company, LLC Early Site Permit, Figures 2.1-3 Through 2.4-1 ML0327306162003-09-25025 September 2003 Site Safety Analysis Report for the Exelon Generation Company, LLC Early Site Permit, Figures 2.4-2 Through 2.4-11 ML0327306172003-09-25025 September 2003 Site Safety Analysis Report for the Exelon Generation Company, LLC Early Site Permit, Figures 2.4-12 Through 2.4-19 ML0327306182003-09-25025 September 2003 Site Safety Analysis Report for the Exelon Generation Company, LLC Early Site Permit, Figures 2.4-20 Through 2.5-5 ML0327306192003-09-25025 September 2003 Site Safety Analysis Report for the Exelon Generation Company, LLC Early Site Permit, Figures 2.5-6 Through Chapter 3, Table 3.3-33 RS-03-013, Request for Amendment to TS 3.6.5.1, Drywell & 5.5.13, Primary Containment Leakage Rate Testing Program2003-01-29029 January 2003 Request for Amendment to TS 3.6.5.1, Drywell & 5.5.13, Primary Containment Leakage Rate Testing Program 2022-06-30 |
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