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Category:Letter type:NG
MONTHYEARNG-23-0010, Supplement to Duane Arnold Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule2023-12-0606 December 2023 Supplement to Duane Arnold Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule NG-23-0009, Part 73 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule2023-11-16016 November 2023 Part 73 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule NG-23-0006, Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update2023-05-23023 May 2023 Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update NG-23-0004, 2022 Annual Radioactive Material Release Report2023-04-25025 April 2023 2022 Annual Radioactive Material Release Report NG-23-0003, 2022 Annual Exposure Report - Form 5s2023-04-21021 April 2023 2022 Annual Exposure Report - Form 5s NG-23-0002, 10 CFR 50.59 Report, Commitment Changes, 10 CFR 72.48 Report, Quality Assurance Program Changes, Technical Specification Basis Changes, and Revision of the DAEC Defueled Safety Analysis Report2023-03-27027 March 2023 10 CFR 50.59 Report, Commitment Changes, 10 CFR 72.48 Report, Quality Assurance Program Changes, Technical Specification Basis Changes, and Revision of the DAEC Defueled Safety Analysis Report NG-23-0001, 2023 Annual Decommissioning and Spent Fuel Management Funding Status Report2023-03-27027 March 2023 2023 Annual Decommissioning and Spent Fuel Management Funding Status Report NG-22-0055, Revision to Duane Arnold Energy Center (DAEC) ISFSI-Only Emergency Plan2022-05-20020 May 2022 Revision to Duane Arnold Energy Center (DAEC) ISFSI-Only Emergency Plan NG-22-0053, 2021 Annual Radiological Environmental Operating Report2022-05-0606 May 2022 2021 Annual Radiological Environmental Operating Report NG-22-0052, Regulatory Issue Summary 2000-11. NRC Emergency Telecommunications System, Statement of Intent to Implement the Proposed Voluntary Initiative2022-05-0404 May 2022 Regulatory Issue Summary 2000-11. NRC Emergency Telecommunications System, Statement of Intent to Implement the Proposed Voluntary Initiative NG-22-0050, Revised Response to Request for Additional Information Relating to Decommissioning Quality Assurance Program, Revision 02022-04-26026 April 2022 Revised Response to Request for Additional Information Relating to Decommissioning Quality Assurance Program, Revision 0 NG-22-0049, 2021 Annual Radioactive Material Release Report2022-04-26026 April 2022 2021 Annual Radioactive Material Release Report NG-22-0035, Response to Request for Additional Information Relating to Decommissioning Quality Assurance Program. Revision 02022-04-13013 April 2022 Response to Request for Additional Information Relating to Decommissioning Quality Assurance Program. Revision 0 NG-22-0047, Registration of Independent Spent Fuel Installation Storage Cask and Notification of Permanent Removal of All Spent Fuel Assemblies from the Spent Fuel Pool2022-04-11011 April 2022 Registration of Independent Spent Fuel Installation Storage Cask and Notification of Permanent Removal of All Spent Fuel Assemblies from the Spent Fuel Pool NG-22-0042, Registration of Independent Spent Fuel Installation Storage Casks2022-04-0808 April 2022 Registration of Independent Spent Fuel Installation Storage Casks NG-22-0041, and Independent Spent Fuel Storage Installation, 2022 Annual Decommissioning and Spent Fuel Management Funding Status Report2022-03-31031 March 2022 and Independent Spent Fuel Storage Installation, 2022 Annual Decommissioning and Spent Fuel Management Funding Status Report NG-22-0031, 2021 Annual Exposure Report - Form 5s2022-03-23023 March 2022 2021 Annual Exposure Report - Form 5s NG-22-0030, Registration of Independent Spent Fuel Installation Storage Casks2022-03-23023 March 2022 Registration of Independent Spent Fuel Installation Storage Casks NG-22-0025, Registration of Independent Spent Fuel Installation Storage Casks2022-03-0808 March 2022 Registration of Independent Spent Fuel Installation Storage Casks NG-22-0021, Registration of Independent Spent Fuel Installation Storage Casks2022-02-24024 February 2022 Registration of Independent Spent Fuel Installation Storage Casks NG-22-0014, Registration of Independent Spent Fuel Installation Storage Casks2022-02-10010 February 2022 Registration of Independent Spent Fuel Installation Storage Casks NG-22-0009, Registration of Independent Spent Fuel Installation Storage Casks2022-01-20020 January 2022 Registration of Independent Spent Fuel Installation Storage Casks NG-22-0001, Supplement to Exemption Request for Failed Fuel Can Weight in a Certificate of Compliance 1004 Renewed Amendment 17 61BTH Type 2 Dry Shielded Canister2022-01-0606 January 2022 Supplement to Exemption Request for Failed Fuel Can Weight in a Certificate of Compliance 1004 Renewed Amendment 17 61BTH Type 2 Dry Shielded Canister NG-21-0038, Registration of Independent Spent Fuel Installation Storage Casks2021-12-22022 December 2021 Registration of Independent Spent Fuel Installation Storage Casks NG-21-0035, Supplement to Exemption Request for Failed Fuel Can Weight in a Certificate of Compliance 1004 Renewed Amendment 17 61 Bth Type 2 Dry Shielded Canister2021-12-10010 December 2021 Supplement to Exemption Request for Failed Fuel Can Weight in a Certificate of Compliance 1004 Renewed Amendment 17 61 Bth Type 2 Dry Shielded Canister NG-21-0030, Exemption Request for Failed Fuel Can Weight in a Certificate of Compliance 1004 Renewed Amendment 17 61 Bth Type 2 Dry Shielded Canister2021-10-21021 October 2021 Exemption Request for Failed Fuel Can Weight in a Certificate of Compliance 1004 Renewed Amendment 17 61 Bth Type 2 Dry Shielded Canister NG-21-0028, Request for Approval of NextEra Energy Duane Arnold, Llc'S Decommissioning Quality Assurance Program Revision 02021-07-30030 July 2021 Request for Approval of NextEra Energy Duane Arnold, Llc'S Decommissioning Quality Assurance Program Revision 0 NG-21-0010, License Amendment Request (TSCR-192): Independent Spent Fuel Storage Installation (ISFSI) Emergency Plan and Emergency Action Level Scheme2021-06-28028 June 2021 License Amendment Request (TSCR-192): Independent Spent Fuel Storage Installation (ISFSI) Emergency Plan and Emergency Action Level Scheme NG-21-0026, CFR 72.48 Report of Changes. Tests. and Experiments2021-06-16016 June 2021 CFR 72.48 Report of Changes. Tests. and Experiments NG-21-0011, Submittal of 2020 Annual Radiological Environmental Operating Report2021-05-0404 May 2021 Submittal of 2020 Annual Radiological Environmental Operating Report NG-21-0009, Report of Facility Changes. Tests and Experiments. and Commitment Changes2021-04-27027 April 2021 Report of Facility Changes. Tests and Experiments. and Commitment Changes NG-21-0021, Supplement to License Amendment Request (TSCR-185): Application to Revise Operating License to Remove Cyber Security Plan Requirements2021-04-22022 April 2021 Supplement to License Amendment Request (TSCR-185): Application to Revise Operating License to Remove Cyber Security Plan Requirements NG-21-0006, 2021 Annual Decommissioning and Spent Fuel Management Funding Status Report2021-03-31031 March 2021 2021 Annual Decommissioning and Spent Fuel Management Funding Status Report NG-21-0005, NextEra Energy Duane Arnold, LLC - Transmittal of the DAEC Defueled Safety Analysis Report Revision 02021-03-29029 March 2021 NextEra Energy Duane Arnold, LLC - Transmittal of the DAEC Defueled Safety Analysis Report Revision 0 NG-20-0094, License Amendment Request (TSCR-189): Revision to Facility License and Technical Specifications to Reflect Permanent Removal of Spent Fuel from the Spent Fuel Pool2021-02-19019 February 2021 License Amendment Request (TSCR-189): Revision to Facility License and Technical Specifications to Reflect Permanent Removal of Spent Fuel from the Spent Fuel Pool NG-21-0004, Response to Request for Additional Information Related to Post Shutdown Decommissioning Activities Report2021-02-0505 February 2021 Response to Request for Additional Information Related to Post Shutdown Decommissioning Activities Report NG-20-0078, Update to Spent Fuel Management Plan Pursuant to 10 CFR 50.54(bb)2021-01-13013 January 2021 Update to Spent Fuel Management Plan Pursuant to 10 CFR 50.54(bb) NG-20-0101, Request for a One-Time Exemption from 10 CFR 73, Appendix B, Section VI, Subsection C.3.(1)(1) Regarding Annual Force-on-Force (FOF) Exercises, Due to COVID-19 Pandemic2020-12-29029 December 2020 Request for a One-Time Exemption from 10 CFR 73, Appendix B, Section VI, Subsection C.3.(1)(1) Regarding Annual Force-on-Force (FOF) Exercises, Due to COVID-19 Pandemic NG-20-0099, Response to Request for Additional Information Relating to License Amendment Request (TSCR-187): Proposed Permanently Defueled Emergency Plan and Permanently Defueled Emergency Action Level Scheme2020-12-0101 December 2020 Response to Request for Additional Information Relating to License Amendment Request (TSCR-187): Proposed Permanently Defueled Emergency Plan and Permanently Defueled Emergency Action Level Scheme NG-20-0093, Supplement to License Amendment Request (TSCR-187): Proposed Permanently Defueled Emergency Plan and Permanently Defueled Emergency Action Level Scheme2020-10-29029 October 2020 Supplement to License Amendment Request (TSCR-187): Proposed Permanently Defueled Emergency Plan and Permanently Defueled Emergency Action Level Scheme NG-20-0090, Certification of Permanent Removal of Fuel from the Reactor Vessel for Duane Arnold Energy Center2020-10-12012 October 2020 Certification of Permanent Removal of Fuel from the Reactor Vessel for Duane Arnold Energy Center NG-20-0083, Registration of Independent Spent Fuel Installation Storage Casks2020-10-12012 October 2020 Registration of Independent Spent Fuel Installation Storage Casks NG-20-0069, Response to Request for Additional Information Relating to Request for Exemption from Portions of 10 CFR 50.47 and 10 CFR 50, Appendix E2020-10-0707 October 2020 Response to Request for Additional Information Relating to Request for Exemption from Portions of 10 CFR 50.47 and 10 CFR 50, Appendix E NG-20-0082, Registration of Independent Spent Fuel Installation Storage Casks2020-09-28028 September 2020 Registration of Independent Spent Fuel Installation Storage Casks NG-20-0071, Request for One-Time Exemption from 10 CFR 50, Appendix E, Biennial Emergency Preparedness Evaluated Exercise Requirements Due to COVID-19 Pandemic2020-09-22022 September 2020 Request for One-Time Exemption from 10 CFR 50, Appendix E, Biennial Emergency Preparedness Evaluated Exercise Requirements Due to COVID-19 Pandemic NG-20-0077, Registration of Independent Spent Fuel Installation Storage Casks2020-09-10010 September 2020 Registration of Independent Spent Fuel Installation Storage Casks NG-20-0073, Notice Regarding Proposed Amendment to Decommissioning Trust Agreements2020-09-0101 September 2020 Notice Regarding Proposed Amendment to Decommissioning Trust Agreements NG-20-0074, Certification of Permanent Cessation of Power Operations2020-08-27027 August 2020 Certification of Permanent Cessation of Power Operations NG-20-0067, Registration of Independent Spent Fuel Installation Storage Casks2020-08-12012 August 2020 Registration of Independent Spent Fuel Installation Storage Casks NG-20-0035, Request for Exemption from 10 CFR 50.54(w)(1)2020-07-16016 July 2020 Request for Exemption from 10 CFR 50.54(w)(1) 2023-05-23
[Table view] Category:Report
MONTHYEARNG-23-0002, 10 CFR 50.59 Report, Commitment Changes, 10 CFR 72.48 Report, Quality Assurance Program Changes, Technical Specification Basis Changes, and Revision of the DAEC Defueled Safety Analysis Report2023-03-27027 March 2023 10 CFR 50.59 Report, Commitment Changes, 10 CFR 72.48 Report, Quality Assurance Program Changes, Technical Specification Basis Changes, and Revision of the DAEC Defueled Safety Analysis Report ML21078A1862021-03-30030 March 2021 Final - Enclosure 2 to LIC-504 Memo - 03/30/2021 ML21078A1782021-03-30030 March 2021 Final of Enclosure 1 - 03/30/2021 NG-21-0005, NextEra Energy Duane Arnold, LLC - Transmittal of the DAEC Defueled Safety Analysis Report Revision 02021-03-29029 March 2021 NextEra Energy Duane Arnold, LLC - Transmittal of the DAEC Defueled Safety Analysis Report Revision 0 ML21042A0792021-02-17017 February 2021 DAEC Executive Summary of Risk Assessment of Derecho Impact on Duane Arnold ML20300A2242020-11-17017 November 2020 Documentation of the Completion of Required Actions Taken in Response to the Lessons Learned from the Fukushima Dai Ichi Accident NG-20-0071, Request for One-Time Exemption from 10 CFR 50, Appendix E, Biennial Emergency Preparedness Evaluated Exercise Requirements Due to COVID-19 Pandemic2020-09-22022 September 2020 Request for One-Time Exemption from 10 CFR 50, Appendix E, Biennial Emergency Preparedness Evaluated Exercise Requirements Due to COVID-19 Pandemic NG-19-0077, Technical Specification 5.6.6 Post Accident Monitoring (PAM) Report2019-06-0606 June 2019 Technical Specification 5.6.6 Post Accident Monitoring (PAM) Report ML18101B4052018-04-18018 April 2018 Staff Assessment of Flooding Focused Evaluation NG-18-0008, Flooding Focused Evaluation Summary2018-01-19019 January 2018 Flooding Focused Evaluation Summary NG-17-0095, Report of Facility Changes, Tests and Experiments, and Commitment Changes2017-05-15015 May 2017 Report of Facility Changes, Tests and Experiments, and Commitment Changes L-2017-014, Florida Power & Light Company - 10 CPR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications for 20162017-04-17017 April 2017 Florida Power & Light Company - 10 CPR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications for 2016 NG-17-0037, Kld TR-910, Duane Arnold Energy Center Development of Evacuation Time Estimates for Revised EPZ Boundary (in Support of License Amendment Request (TSCR-165))2017-03-0909 March 2017 Kld TR-910, Duane Arnold Energy Center Development of Evacuation Time Estimates for Revised EPZ Boundary (in Support of License Amendment Request (TSCR-165)) ML16271A3742016-09-23023 September 2016 Technical Requirements Manual (TRM)-Appendix a, Revision 0 - Pressure and Temperature Limits Report (PTLR) for 54 Effective Full-Power Years (EFPY) NG-15-0344, Technical Specification 5.6.6 Post Accident Monitoring (PAM) Report December 20152015-12-10010 December 2015 Technical Specification 5.6.6 Post Accident Monitoring (PAM) Report December 2015 ML15253A3112015-07-30030 July 2015 Pressure and Temperature Limits Report (PTLR) for 32 and 54 Effective Full-Power Years (EFPY) NG-15-0128, Submittal of Report of Facility Changes, Tests and Experiments, and Commitment Changes2015-05-13013 May 2015 Submittal of Report of Facility Changes, Tests and Experiments, and Commitment Changes ML16076A2092014-12-31031 December 2014 Redacted Non-Proprietary BWRVIP-135, Revision 3: BWR Vessel and Internals Project NG-16-0042, BWRVIP-135, Revision 3: BWR Vessel and Internal Project - Integrated Surveillance Program (ISP) Data Source Book and Plant Evaluations2014-12-31031 December 2014 BWRVIP-135, Revision 3: BWR Vessel and Internal Project - Integrated Surveillance Program (ISP) Data Source Book and Plant Evaluations NG-14-0155, 10 CFR 50.46 30-Day Special Report of Changes in Peak Cladding Temperature2014-06-19019 June 2014 10 CFR 50.46 30-Day Special Report of Changes in Peak Cladding Temperature ML14105A4522014-05-22022 May 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukshima DAI-ICHI Nuclear Power Plant Accident ML14045A1652014-02-13013 February 2014 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Duane Arnold Energy Center, TAC No.: MF1000 ML13308A3172013-10-29029 October 2013 DAEC-SDP-2013-001 - PRA Risk Assessment, 'A' EDG Lube Oil Cooler Leak NG-12-0487, Development of Evacuation Time Estimates2012-12-21021 December 2012 Development of Evacuation Time Estimates NG-12-0467, Seismic Walkdown Report, in Response to the 50.54(f) Information Request Re Fukushima Near-Term Task Force Recommendation 2.3: Seismic2012-11-27027 November 2012 Seismic Walkdown Report, in Response to the 50.54(f) Information Request Re Fukushima Near-Term Task Force Recommendation 2.3: Seismic ML12342A0052012-11-15015 November 2012 Flooding Walkdown Report NEE006-PR-001, Revision 0, in Response to the 50.54(f) Information Request Regarding Near-Term Task Force Recommendation 2.3: Flooding for the Duane Arnold Energy Center ML17363A0832012-11-14014 November 2012 Flooding Walkdown Report, NEE006-PR-001, Revision 0 ML12187A1632012-06-22022 June 2012 TRM Revision Update Instructions, Regional Library TRM, Rev. 22 ML12158A4922012-06-0808 June 2012 Review of 60-Day Response to Request for Information Regarding Recommendation 9.-3 of the Near-Term Task Force Related Tot He Fukushima Daiichi Nuclear Power Plant Accident ML1127000692011-09-26026 September 2011 Enclosure 2, Mfn 10-245 R4, Description of the Evaluation and Surveillance Recommendations for BWR/2-5 Plants ML0920301852009-08-0707 August 2009 Issuance of the Environmental Scoping Summary Report for the Staff'S Review of the License Renewal Application for Duane Arnold Energy Center ML0920101962009-08-0303 August 2009 Idnr, 2009, Amendment to NPDES Permit, Permit #5700104, Prepared by W. Hieb, NPDES Permits Section, May 18 (Accessed June 16, 2009) ML0920102122009-08-0303 August 2009 EPA, 2009, Enforcement & Compliance History Online (Echo) (Accessed June 4, 2009) ML0920102042009-07-17017 July 2009 Idnr, 2009, NPDES Permit IA0003727 (Duane Arnold Energy Center) Detailed Reports, Water Discharge Permits, Permit Compliance System (Accessed June 4, 2009) ML0905701892008-11-20020 November 2008 Energysolutions - Document No. 82A9634, Revision 0, Decommissioning Cost Estimate Study for the Duane Arnold Energy Center. ML0821900132008-08-0707 August 2008 Monthly Operating Reports Second Quarter 2008 NG-08-0239, Three Month Response to NRC Generic Letter 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems2008-05-0808 May 2008 Three Month Response to NRC Generic Letter 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems L-2006-180, Sation; St. Lucie, Units 1 and 2 and Turkey Point, Units 3 and 4 - Groundwater Questionnaire2006-07-31031 July 2006 Sation; St. Lucie, Units 1 and 2 and Turkey Point, Units 3 and 4 - Groundwater Questionnaire NG-05-0563, Supplemental Information in Support of Application for Order and Conforming Amendments for License Transfer2005-10-11011 October 2005 Supplemental Information in Support of Application for Order and Conforming Amendments for License Transfer ML0522700732005-04-18018 April 2005 Event Notification Report for April 18, 2005 ML0435700172004-12-14014 December 2004 from NMC Re Technical Evaluation of Proposed Method of Class 3 Pipe Leak Operability Determinations ML0406308002004-02-17017 February 2004 Transmittal of Fitness-for-Duty Performance Data for Period Ending June 30, 2003 ML0802902312004-02-12012 February 2004 Westinghouse Technical Bulletin: Information Regarding Recent Crossflow Ultrasonic Flow Measurement System Performance Observations, TB-04-4 NG-04-0082, Request for Relief from ASME Section XI, Appendix Viii, Supplement 11 Requirements2004-02-12012 February 2004 Request for Relief from ASME Section XI, Appendix Viii, Supplement 11 Requirements NG-03-0608, Revised Non-Proprietary GE Report GE-NE-A22-00100-08-01a-R2, Pressure-Temperature Curves for Duane Arnold Energy Center2003-08-18018 August 2003 Revised Non-Proprietary GE Report GE-NE-A22-00100-08-01a-R2, Pressure-Temperature Curves for Duane Arnold Energy Center ML0318909462003-07-10010 July 2003 Relaxation of the Order, Exercising Enforcement Discretion, and Extension of the Time to Submit an Answer or Request a Hearing Regarding Order EA-03-038, Fitness-for-Duty Enhancements for Nuclear Security Force Personnel for Duane Arnold, K NG-03-0474, Revised Pages for General Electric Co. Report, GE-NE-A22-00100-08-01-R1, Pressure-Temperature Curves for Alliant Energy Duane Arnold Energy Center.2003-06-30030 June 2003 Revised Pages for General Electric Co. Report, GE-NE-A22-00100-08-01-R1, Pressure-Temperature Curves for Alliant Energy Duane Arnold Energy Center. NG-03-0123, Technical Specification Change Request (TSCR-059): Adoption of Generic Letter 96-03: 'Relocation of Pressure Temperature Limit Curves & Low Temperature Overpressure Protection System Limits.'2003-02-28028 February 2003 Technical Specification Change Request (TSCR-059): Adoption of Generic Letter 96-03: 'Relocation of Pressure Temperature Limit Curves & Low Temperature Overpressure Protection System Limits.' ML0230106302002-09-19019 September 2002 GE Technology R704B Simulator Course Lesson Plan NRC Generic Letter 1979-451979-09-25025 September 1979 NRC Generic Letter 1979-045: Transmittal of Reports Regarding Foreign Reactor Operation Experiences 2023-03-27
[Table view] Category:Technical
MONTHYEARNG-23-0002, 10 CFR 50.59 Report, Commitment Changes, 10 CFR 72.48 Report, Quality Assurance Program Changes, Technical Specification Basis Changes, and Revision of the DAEC Defueled Safety Analysis Report2023-03-27027 March 2023 10 CFR 50.59 Report, Commitment Changes, 10 CFR 72.48 Report, Quality Assurance Program Changes, Technical Specification Basis Changes, and Revision of the DAEC Defueled Safety Analysis Report ML21078A1862021-03-30030 March 2021 Final - Enclosure 2 to LIC-504 Memo - 03/30/2021 ML21078A1782021-03-30030 March 2021 Final of Enclosure 1 - 03/30/2021 NG-21-0005, NextEra Energy Duane Arnold, LLC - Transmittal of the DAEC Defueled Safety Analysis Report Revision 02021-03-29029 March 2021 NextEra Energy Duane Arnold, LLC - Transmittal of the DAEC Defueled Safety Analysis Report Revision 0 ML20300A2242020-11-17017 November 2020 Documentation of the Completion of Required Actions Taken in Response to the Lessons Learned from the Fukushima Dai Ichi Accident NG-19-0077, Technical Specification 5.6.6 Post Accident Monitoring (PAM) Report2019-06-0606 June 2019 Technical Specification 5.6.6 Post Accident Monitoring (PAM) Report NG-18-0008, Flooding Focused Evaluation Summary2018-01-19019 January 2018 Flooding Focused Evaluation Summary NG-17-0037, Kld TR-910, Duane Arnold Energy Center Development of Evacuation Time Estimates for Revised EPZ Boundary (in Support of License Amendment Request (TSCR-165))2017-03-0909 March 2017 Kld TR-910, Duane Arnold Energy Center Development of Evacuation Time Estimates for Revised EPZ Boundary (in Support of License Amendment Request (TSCR-165)) NG-15-0344, Technical Specification 5.6.6 Post Accident Monitoring (PAM) Report December 20152015-12-10010 December 2015 Technical Specification 5.6.6 Post Accident Monitoring (PAM) Report December 2015 ML16076A2092014-12-31031 December 2014 Redacted Non-Proprietary BWRVIP-135, Revision 3: BWR Vessel and Internals Project NG-16-0042, BWRVIP-135, Revision 3: BWR Vessel and Internal Project - Integrated Surveillance Program (ISP) Data Source Book and Plant Evaluations2014-12-31031 December 2014 BWRVIP-135, Revision 3: BWR Vessel and Internal Project - Integrated Surveillance Program (ISP) Data Source Book and Plant Evaluations ML14045A1652014-02-13013 February 2014 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Duane Arnold Energy Center, TAC No.: MF1000 ML13308A3172013-10-29029 October 2013 DAEC-SDP-2013-001 - PRA Risk Assessment, 'A' EDG Lube Oil Cooler Leak ML17363A0832012-11-14014 November 2012 Flooding Walkdown Report, NEE006-PR-001, Revision 0 ML12187A1632012-06-22022 June 2012 TRM Revision Update Instructions, Regional Library TRM, Rev. 22 ML0905701892008-11-20020 November 2008 Energysolutions - Document No. 82A9634, Revision 0, Decommissioning Cost Estimate Study for the Duane Arnold Energy Center. ML0821900132008-08-0707 August 2008 Monthly Operating Reports Second Quarter 2008 NG-05-0563, Supplemental Information in Support of Application for Order and Conforming Amendments for License Transfer2005-10-11011 October 2005 Supplemental Information in Support of Application for Order and Conforming Amendments for License Transfer ML0435700172004-12-14014 December 2004 from NMC Re Technical Evaluation of Proposed Method of Class 3 Pipe Leak Operability Determinations ML0802902312004-02-12012 February 2004 Westinghouse Technical Bulletin: Information Regarding Recent Crossflow Ultrasonic Flow Measurement System Performance Observations, TB-04-4 NG-03-0608, Revised Non-Proprietary GE Report GE-NE-A22-00100-08-01a-R2, Pressure-Temperature Curves for Duane Arnold Energy Center2003-08-18018 August 2003 Revised Non-Proprietary GE Report GE-NE-A22-00100-08-01a-R2, Pressure-Temperature Curves for Duane Arnold Energy Center NG-03-0474, Revised Pages for General Electric Co. Report, GE-NE-A22-00100-08-01-R1, Pressure-Temperature Curves for Alliant Energy Duane Arnold Energy Center.2003-06-30030 June 2003 Revised Pages for General Electric Co. Report, GE-NE-A22-00100-08-01-R1, Pressure-Temperature Curves for Alliant Energy Duane Arnold Energy Center. NG-03-0123, Technical Specification Change Request (TSCR-059): Adoption of Generic Letter 96-03: 'Relocation of Pressure Temperature Limit Curves & Low Temperature Overpressure Protection System Limits.'2003-02-28028 February 2003 Technical Specification Change Request (TSCR-059): Adoption of Generic Letter 96-03: 'Relocation of Pressure Temperature Limit Curves & Low Temperature Overpressure Protection System Limits.' ML0230106302002-09-19019 September 2002 GE Technology R704B Simulator Course Lesson Plan NRC Generic Letter 1979-451979-09-25025 September 1979 NRC Generic Letter 1979-045: Transmittal of Reports Regarding Foreign Reactor Operation Experiences 2023-03-27
[Table view] |
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N~ExTera M EN ERGY~ DUANE ARNOLD December 10, 2015 NG-1 5-0344 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555-0001 Duane Arnold Energy Center Docket 50-331 Renewed Op. License No. DPR-49 Technical Specification 5.6.6 Post Accident Monitoring (PAM) Report, December 2015 The purpose of this letter is to submit the attached report required by the Duane Arnold Energy Center Technical Specifications (TS) Section 5.6.6, Post Accident Monitoring (PAM) Report. This letter makes no new commitments or changes to any existing commitments.
T. A. Vehec NextEra Energy Duane Arnold, LLC
Enclosure:
Technical Specification 5.6.6 Post-Accident Monitoring (PAM) Report, December, 2015 cc: Administrator, Region Ill, USNRC Project Manager, DAEC, USNRC Resident Inspector, DAEC, USNRC
/~O6/
(44L NextEra Energy Duane Arnold, LLC, 3277 DAEC Road, Palo, IA 52324
Enclosure to NG-15-0344 Technical Specification 5.6.6 Post-Accident Monitorinq (PAM) Report, December, 2015 4 pages follow
Enclosure to NG-1 5-0344 Technical Specification 5.6.6 Post-Accident Monitoring (PAM) Instrumentation 14-Day Report. December 10. 2015
Background
On November 3, 2015 at 0910, while operating at 100% power, a Control Room operator cycled CV4639, the Inboard Recirculation Sample Primary Containment Isolation Valve (PCIV) and a loss of PoSt Accident Monitoring (PAM) valve position indication occurred. This required an entry into a Technical Specifications (TS) inoperability condition for CV4639 open position indication.
No automatic actions such as PCIV closure were prevented by the CV4639 open position indication failure. The open position indication of CV4639 was considered inoperable and required an entry into TS Section 3.3.3.1, "Post Accident Monitoring (PAM) Instrumentation" Condition A, as Function 6 in Table 3.3.3.1-1 (PCIV position) was not Operable for CV4639. Condition A requires restoration of the required indication channel to an Operable status within 30 days. Resolution of the issue within 30 days (December 3, 2015) was not achieved, then requiring, per TS 3.3.3.1 Condition B, that a report be submitted within the following 14 days (December 17, 2015) in accordance with TS Section 5.6.6. "PAM Report".
The TS 5.6.6 PAM report requirement states the cause of the inoperability is to be discussed along with plans for restoration. The report requirement also assumes the condition has not been corrected and as such calls for outlining alternate monitoring methods and their equivalency to the lost function, or justification of non-equivalency.
There was a prior occurrence of the open CV4639 position indication issue on September 9, 2015, and although the indication was subsequently restored to Operable but Degraded status, a PAM report was submitted on October 22, 2015 (NG-15-0315) since the 30-day LCO was exceeded. This report noted that an Adverse Condition Monitoring Plan (ACMP) was now in use during CV4639 cycling, and alternate monitoring would be implemented if the CV4639 open indication became inoperable prior to final resolution of the cause of the issue. This alternate monitoring was implemented on November 3, 2015 following identification of the inoperability condition for CV4639 open position indication._
Cause of the Inoperability The most likely cause of the loss of the Control Room indication of CV4639 open position is a spring in the open position indicating limit switch that can have reduced force when operating in its current environmental conditions. This limit switch is Page 1 of 4
Enclosure to NG-15-0344 located inside the Primary Containment within the drywell structure, so it is not accessible during plant operation. The cause analysis with extent of condition will be finalized when drywell entry is possible.
The CV4639 open position indicating limit switch was installed in October 2014 during a refueling outage. The manufacturer, NAMCO, submitted a 100FR 21 .21 (d)(3)(i)
(Part 21) report (Event Notification 51280) on July 31, 2015 documenting that one lot of springs that are internal to the limit switch model (EA180-31402) has a reduced spring force when in a continuous ambient temperature above 123°F, meaning the limit switch will not consistently return to its initial, unactuated, position. In August, 2015 as part of the plant's Part 21 impact review, it was determined the open position limit switch of CV4639, installed October 15, 2014, was the sole plant component having a spring from the suspect lot. The switch is located in an area of the drywell where operating temperatures are between 130°F and 145°F during power operation.
For CV4639, the "initial, unactuated position" corresponds to an illuminated red (open) light. A work request was initiated as part of the Part 21 review to replace the limit switch during a plant shutdown when drywell access is permitted. There has been no plant shutdown since that time. The indication provided by this limit switch is also used for valve closing time testing.
Following the November 3, 2015 event, CV4639 was cycled 8 times, but after the initial closure of the valve, the open indication (red light) never returned when the valve was re-opened. The ACMP directions for alternate monitoring were used to confirm that the valve itself was open. The Part 21 notice states the reduced spring force only affects the switch's ability to return to its initial, unactuated position, not its ability to maintain the unactuated position. The open indication (red light) is the unactuated position. The closing force of CV4639 overcomes the limit switch spring force to turn the red light off. The purpose of the (reduced force) spring in this application is to turn the red light back on after a full valve closure. CV4639 is maintained in the open (red) position during online operation (Modes 1, 2 and 3) except during quarterly testing. With the red light on, the PAM function of verifying CV4639 closed upon a Primary Containment Isolation signal can be successfully completed. However, as noted, on November 3 the red light remained off even after several attempts were made to restore the indication by cycling CV4639 via the Control Room hand switch.
Alternate Method of Monitoring Only the red light is on when CV4639 is open and only the green light is on when CV4639 is closed. If CV4639 is intermediate, both lights are on. With the open (red) indication not working, a full open valve position can be deduced if there is not a green Page 2 of 4
Enclosure to NG-1 5-0344 (closed) light. However, if there is a green (closed) light, it is not possible to determine if the CV4639 valve position is intermediate (red and green lights) or the flow path is isolated (green light only).
As previously noted, an Adverse Condition Monitoring Plan had already been established to monitor the CV4639 Control Room open (red) indication whenever the valve was cycled. The ACMP required that if loss of the red light with the valve open occurred, the CV4639 PAM valve position indication function would be declared Inoperable, and alternate monitoring of valve position would be implemented until position indication operability could be restored.
The outboard isolation valve on the line, CV4640, is Operable, including its indication.
No isolation signal was present and CV4640 was in the open position at the time of the CV4639 position indication inoperability. The ACMP requires confirmation of the Primary Containment penetration's status, and directs use of a process computer point available in the Control Room that monitors flow through the penetration for the Crack Arrest Verification (CAV) system. Ongoing flow through the penetration was indicated by the computer point, indicating CV4639 was also open and the penetration was not isolated.
Under current conditions, if CV4640 is closed, its position indication in the Control Room will confirm the penetration is isolated. Should there be simultaneous issues with both CV4639 and CV4640 valve position indication, the CAV flow measurement could be used to confirm penetration isolation.
Degree of Equivalence of Alternate Indication Through the use of the CAV computer point, the ability to determine CV4639 position, if needed, will remain available in the Control Room. The CAV flow measurement can be used in the Control Room to confirm pe~netration isolation, and in conjunction with the CV4640 position indication, the CAV measurement can also indicate when CV4639 is in the open position.
Justification of Areas of Alternate Indication Non-Equivalency The computer providing the CAV flow indication is not seismically qualified, however, based on engineering judgment it is sufficiently robust to monitor flow in the design basis event. The flow element which serves it does not require electric power. The Page 3 of 4
Enclosure to NG-15-0344 flow transmitter and computer that receives the signal are energized from a lighting panel that is powered by an essential power supply (1 B35).
No automatic actions (such as penetration isolation) are prevented by the inoperability of the CV4639 open indication. Based on engineering judgment, the alternate method available to determine the status of the Recirculation Sample penetration provides operators with suitable reliable indication.
Plans and Schedule for Resolving the Operable but Degraded Condition Replacement of the limit switch for CV4639 to correct the condition identified in the NAMCO Controls Part 21 notice requires a plant shutdown with drywell entry. The limit switch will be replaced as opportunity allows and no later than the next scheduled refueling outage (currently October 2016).
Assessment of Safety Consequences:
The Primary Containment penetration in question is served by isolation valves CV4639 and CV4640 in series. Both of these valves receive a close signal when conditions require isolation of Primary Containment. Each of these PCIVs has position indication in the Control Room. The closed (green) and open (red) position indications remained Operable for CV4640, the Outboard Recirculation Sample PCIV.
The closed (green) position indication also remained Operable for CV4639. The open (red) indication for CV4639 is Inoperable. With the CV4639 open position indication not available, neither intermediate nor open CV4639 valve position is directly indicated in the Control Room.
With CV4640 and its position indication Operable, upon isolation of Primary Containment the Control Room operators would be able to verify the closed (isolated) status of the penetration flow path. If CV4640, or its indication, are rendered Inoperable the Control Room will use the alternate indication method given in the ACMP to verify the penetration flow path is closed. The loss of the CV4639 open indication represents a loss of redundancy with respect to the capability of verifying that Primary Containment isolation of the Recirculation sample line penetration had been achieved. The valve position indication is independent from valve operation, and the actual capability of CV4639 to isolate upon a Primary Containment Isolation signal is not impacted.
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N~ExTera M EN ERGY~ DUANE ARNOLD December 10, 2015 NG-1 5-0344 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555-0001 Duane Arnold Energy Center Docket 50-331 Renewed Op. License No. DPR-49 Technical Specification 5.6.6 Post Accident Monitoring (PAM) Report, December 2015 The purpose of this letter is to submit the attached report required by the Duane Arnold Energy Center Technical Specifications (TS) Section 5.6.6, Post Accident Monitoring (PAM) Report. This letter makes no new commitments or changes to any existing commitments.
T. A. Vehec NextEra Energy Duane Arnold, LLC
Enclosure:
Technical Specification 5.6.6 Post-Accident Monitoring (PAM) Report, December, 2015 cc: Administrator, Region Ill, USNRC Project Manager, DAEC, USNRC Resident Inspector, DAEC, USNRC
/~O6/
(44L NextEra Energy Duane Arnold, LLC, 3277 DAEC Road, Palo, IA 52324
Enclosure to NG-15-0344 Technical Specification 5.6.6 Post-Accident Monitorinq (PAM) Report, December, 2015 4 pages follow
Enclosure to NG-1 5-0344 Technical Specification 5.6.6 Post-Accident Monitoring (PAM) Instrumentation 14-Day Report. December 10. 2015
Background
On November 3, 2015 at 0910, while operating at 100% power, a Control Room operator cycled CV4639, the Inboard Recirculation Sample Primary Containment Isolation Valve (PCIV) and a loss of PoSt Accident Monitoring (PAM) valve position indication occurred. This required an entry into a Technical Specifications (TS) inoperability condition for CV4639 open position indication.
No automatic actions such as PCIV closure were prevented by the CV4639 open position indication failure. The open position indication of CV4639 was considered inoperable and required an entry into TS Section 3.3.3.1, "Post Accident Monitoring (PAM) Instrumentation" Condition A, as Function 6 in Table 3.3.3.1-1 (PCIV position) was not Operable for CV4639. Condition A requires restoration of the required indication channel to an Operable status within 30 days. Resolution of the issue within 30 days (December 3, 2015) was not achieved, then requiring, per TS 3.3.3.1 Condition B, that a report be submitted within the following 14 days (December 17, 2015) in accordance with TS Section 5.6.6. "PAM Report".
The TS 5.6.6 PAM report requirement states the cause of the inoperability is to be discussed along with plans for restoration. The report requirement also assumes the condition has not been corrected and as such calls for outlining alternate monitoring methods and their equivalency to the lost function, or justification of non-equivalency.
There was a prior occurrence of the open CV4639 position indication issue on September 9, 2015, and although the indication was subsequently restored to Operable but Degraded status, a PAM report was submitted on October 22, 2015 (NG-15-0315) since the 30-day LCO was exceeded. This report noted that an Adverse Condition Monitoring Plan (ACMP) was now in use during CV4639 cycling, and alternate monitoring would be implemented if the CV4639 open indication became inoperable prior to final resolution of the cause of the issue. This alternate monitoring was implemented on November 3, 2015 following identification of the inoperability condition for CV4639 open position indication._
Cause of the Inoperability The most likely cause of the loss of the Control Room indication of CV4639 open position is a spring in the open position indicating limit switch that can have reduced force when operating in its current environmental conditions. This limit switch is Page 1 of 4
Enclosure to NG-15-0344 located inside the Primary Containment within the drywell structure, so it is not accessible during plant operation. The cause analysis with extent of condition will be finalized when drywell entry is possible.
The CV4639 open position indicating limit switch was installed in October 2014 during a refueling outage. The manufacturer, NAMCO, submitted a 100FR 21 .21 (d)(3)(i)
(Part 21) report (Event Notification 51280) on July 31, 2015 documenting that one lot of springs that are internal to the limit switch model (EA180-31402) has a reduced spring force when in a continuous ambient temperature above 123°F, meaning the limit switch will not consistently return to its initial, unactuated, position. In August, 2015 as part of the plant's Part 21 impact review, it was determined the open position limit switch of CV4639, installed October 15, 2014, was the sole plant component having a spring from the suspect lot. The switch is located in an area of the drywell where operating temperatures are between 130°F and 145°F during power operation.
For CV4639, the "initial, unactuated position" corresponds to an illuminated red (open) light. A work request was initiated as part of the Part 21 review to replace the limit switch during a plant shutdown when drywell access is permitted. There has been no plant shutdown since that time. The indication provided by this limit switch is also used for valve closing time testing.
Following the November 3, 2015 event, CV4639 was cycled 8 times, but after the initial closure of the valve, the open indication (red light) never returned when the valve was re-opened. The ACMP directions for alternate monitoring were used to confirm that the valve itself was open. The Part 21 notice states the reduced spring force only affects the switch's ability to return to its initial, unactuated position, not its ability to maintain the unactuated position. The open indication (red light) is the unactuated position. The closing force of CV4639 overcomes the limit switch spring force to turn the red light off. The purpose of the (reduced force) spring in this application is to turn the red light back on after a full valve closure. CV4639 is maintained in the open (red) position during online operation (Modes 1, 2 and 3) except during quarterly testing. With the red light on, the PAM function of verifying CV4639 closed upon a Primary Containment Isolation signal can be successfully completed. However, as noted, on November 3 the red light remained off even after several attempts were made to restore the indication by cycling CV4639 via the Control Room hand switch.
Alternate Method of Monitoring Only the red light is on when CV4639 is open and only the green light is on when CV4639 is closed. If CV4639 is intermediate, both lights are on. With the open (red) indication not working, a full open valve position can be deduced if there is not a green Page 2 of 4
Enclosure to NG-1 5-0344 (closed) light. However, if there is a green (closed) light, it is not possible to determine if the CV4639 valve position is intermediate (red and green lights) or the flow path is isolated (green light only).
As previously noted, an Adverse Condition Monitoring Plan had already been established to monitor the CV4639 Control Room open (red) indication whenever the valve was cycled. The ACMP required that if loss of the red light with the valve open occurred, the CV4639 PAM valve position indication function would be declared Inoperable, and alternate monitoring of valve position would be implemented until position indication operability could be restored.
The outboard isolation valve on the line, CV4640, is Operable, including its indication.
No isolation signal was present and CV4640 was in the open position at the time of the CV4639 position indication inoperability. The ACMP requires confirmation of the Primary Containment penetration's status, and directs use of a process computer point available in the Control Room that monitors flow through the penetration for the Crack Arrest Verification (CAV) system. Ongoing flow through the penetration was indicated by the computer point, indicating CV4639 was also open and the penetration was not isolated.
Under current conditions, if CV4640 is closed, its position indication in the Control Room will confirm the penetration is isolated. Should there be simultaneous issues with both CV4639 and CV4640 valve position indication, the CAV flow measurement could be used to confirm penetration isolation.
Degree of Equivalence of Alternate Indication Through the use of the CAV computer point, the ability to determine CV4639 position, if needed, will remain available in the Control Room. The CAV flow measurement can be used in the Control Room to confirm pe~netration isolation, and in conjunction with the CV4640 position indication, the CAV measurement can also indicate when CV4639 is in the open position.
Justification of Areas of Alternate Indication Non-Equivalency The computer providing the CAV flow indication is not seismically qualified, however, based on engineering judgment it is sufficiently robust to monitor flow in the design basis event. The flow element which serves it does not require electric power. The Page 3 of 4
Enclosure to NG-15-0344 flow transmitter and computer that receives the signal are energized from a lighting panel that is powered by an essential power supply (1 B35).
No automatic actions (such as penetration isolation) are prevented by the inoperability of the CV4639 open indication. Based on engineering judgment, the alternate method available to determine the status of the Recirculation Sample penetration provides operators with suitable reliable indication.
Plans and Schedule for Resolving the Operable but Degraded Condition Replacement of the limit switch for CV4639 to correct the condition identified in the NAMCO Controls Part 21 notice requires a plant shutdown with drywell entry. The limit switch will be replaced as opportunity allows and no later than the next scheduled refueling outage (currently October 2016).
Assessment of Safety Consequences:
The Primary Containment penetration in question is served by isolation valves CV4639 and CV4640 in series. Both of these valves receive a close signal when conditions require isolation of Primary Containment. Each of these PCIVs has position indication in the Control Room. The closed (green) and open (red) position indications remained Operable for CV4640, the Outboard Recirculation Sample PCIV.
The closed (green) position indication also remained Operable for CV4639. The open (red) indication for CV4639 is Inoperable. With the CV4639 open position indication not available, neither intermediate nor open CV4639 valve position is directly indicated in the Control Room.
With CV4640 and its position indication Operable, upon isolation of Primary Containment the Control Room operators would be able to verify the closed (isolated) status of the penetration flow path. If CV4640, or its indication, are rendered Inoperable the Control Room will use the alternate indication method given in the ACMP to verify the penetration flow path is closed. The loss of the CV4639 open indication represents a loss of redundancy with respect to the capability of verifying that Primary Containment isolation of the Recirculation sample line penetration had been achieved. The valve position indication is independent from valve operation, and the actual capability of CV4639 to isolate upon a Primary Containment Isolation signal is not impacted.
Page 4 of 4