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Category:Letter type:RA
MONTHYEARRA-24-0191, Submittal of Updated Final Safety Analysis Report (Revision 24), Technical Specification Bases Revisions, Ufsar/Selected Licensee Commitment Changes, 10 CFR 50.59 Evaluation Summary Report, and Notification of2024-10-22022 October 2024 Submittal of Updated Final Safety Analysis Report (Revision 24), Technical Specification Bases Revisions, Ufsar/Selected Licensee Commitment Changes, 10 CFR 50.59 Evaluation Summary Report, and Notification of RA-24-0259, Transmittal of Core Operating Limits Reports (COLR) for Oconee Nuclear Station (ONS) Unit 1 Cycle 33 (Revision 2), ONS Unit 2 Cycle 32 (Revision 1 and ONS Unit 3 Cycle 33 (Revisions O and 1)2024-10-16016 October 2024 Transmittal of Core Operating Limits Reports (COLR) for Oconee Nuclear Station (ONS) Unit 1 Cycle 33 (Revision 2), ONS Unit 2 Cycle 32 (Revision 1 and ONS Unit 3 Cycle 33 (Revisions O and 1) RA-24-0254, Resubmittal of Relief Requested in Accordance with 10 CFR 50.55a(g)(5)(iii) for Volumetric Examination of Class 1 Components2024-10-14014 October 2024 Resubmittal of Relief Requested in Accordance with 10 CFR 50.55a(g)(5)(iii) for Volumetric Examination of Class 1 Components RA-24-0247, Core Operating Limits Report (COLR) for Unit 1 Cycle 29 Reload Core2024-10-0707 October 2024 Core Operating Limits Report (COLR) for Unit 1 Cycle 29 Reload Core RA-24-0258, Reply to a Notice of Violation; EA-24-0492024-10-0707 October 2024 Reply to a Notice of Violation; EA-24-049 RA-24-0244, Snubber Program Plan Revision, AD-EG-ONS-1618, Oconee Nuclear Station Snubber Program Plan2024-09-30030 September 2024 Snubber Program Plan Revision, AD-EG-ONS-1618, Oconee Nuclear Station Snubber Program Plan RA-24-0229, Transmittal of Refuel 32 (O3R32) Inservice Inspection (ISI) Report, Fifth 10-Year ISI Interval2024-09-23023 September 2024 Transmittal of Refuel 32 (O3R32) Inservice Inspection (ISI) Report, Fifth 10-Year ISI Interval RA-24-0193, Supplement to Proposed Alternative for the Inspection of Reactor Vessel Closure Head Penetrations in Accordance with 10 CFR 50.55a(z)(2)2024-08-28028 August 2024 Supplement to Proposed Alternative for the Inspection of Reactor Vessel Closure Head Penetrations in Accordance with 10 CFR 50.55a(z)(2) RA-24-0185, Snubber Program Plan - Snubber Program Plan Revision, AD-EG-MNS-16182024-08-28028 August 2024 Snubber Program Plan - Snubber Program Plan Revision, AD-EG-MNS-1618 RA-24-0215, Registration for Use of General License Spent Fuel Cask Numbers 177 and 1782024-08-15015 August 2024 Registration for Use of General License Spent Fuel Cask Numbers 177 and 178 RA-24-0208, Refuel 26 (C2R26) Inservice Inspection (ISI) Report2024-08-12012 August 2024 Refuel 26 (C2R26) Inservice Inspection (ISI) Report RA-24-0209, Regulatory Conference, Additional Supporting Information2024-08-0606 August 2024 Regulatory Conference, Additional Supporting Information RA-24-0197, Subsequent License Renewal Application Response to Request for Additional Information 2024 Annual Update and Subsequent License Renewal Application Supplement 5 Addition2024-07-31031 July 2024 Subsequent License Renewal Application Response to Request for Additional Information 2024 Annual Update and Subsequent License Renewal Application Supplement 5 Addition RA-24-0203, Regulatory Conference Supporting Information2024-07-31031 July 2024 Regulatory Conference Supporting Information RA-24-0092, Application to Revise Technical Specification 3.7.7, Low Pressure Service Water (LPSW) System, to Extend the Completion Time for One Required LPSW Pump Inoperable on a One-Time Basis2024-07-29029 July 2024 Application to Revise Technical Specification 3.7.7, Low Pressure Service Water (LPSW) System, to Extend the Completion Time for One Required LPSW Pump Inoperable on a One-Time Basis RA-24-0137, Relief Requests for Inservice Testing Plan – Fifth Interval2024-07-0101 July 2024 Relief Requests for Inservice Testing Plan – Fifth Interval RA-23-0245, License Amendment Request Proposing to Revise Technical Specification 3.4.3, RCS Pressure and Temperature (P/T) Limits2024-06-18018 June 2024 License Amendment Request Proposing to Revise Technical Specification 3.4.3, RCS Pressure and Temperature (P/T) Limits RA-24-0136, Subsequent License Renewal Application Third Annual Update to the License Renewal Application and Subsequent License Renewal Application Supplement 52024-05-24024 May 2024 Subsequent License Renewal Application Third Annual Update to the License Renewal Application and Subsequent License Renewal Application Supplement 5 RA-23-0028, Application to Revise Technical Specifications to Adopt TSTF-234-A, Revision 1, Add Action for More than One (D)Rpi Inoperable2024-05-23023 May 2024 Application to Revise Technical Specifications to Adopt TSTF-234-A, Revision 1, Add Action for More than One (D)Rpi Inoperable RA-24-0152, Duke Energy Carolinas, LLC - Request to Use a Provision of a Later Edition and Addenda of the ASME Boiler and Pressure Vessel Code, Section XI2024-05-22022 May 2024 Duke Energy Carolinas, LLC - Request to Use a Provision of a Later Edition and Addenda of the ASME Boiler and Pressure Vessel Code, Section XI RA-24-0132, Transmittal of Oconee Unit 2, Refuel 31 (O2R31) Steam Generator Tube Inspection Report2024-05-14014 May 2024 Transmittal of Oconee Unit 2, Refuel 31 (O2R31) Steam Generator Tube Inspection Report RA-24-0030, Duke Energy - Annual Radioactive Effluent Release Report - 20232024-04-29029 April 2024 Duke Energy - Annual Radioactive Effluent Release Report - 2023 RA-24-0083, Annual Report of Changes Pursuant to 10 CFR 50.462024-04-25025 April 2024 Annual Report of Changes Pursuant to 10 CFR 50.46 RA-24-0096, Instrumentation and Control Safety Systems NRC Review of Framatome TXS-Compact Topical Report2024-04-24024 April 2024 Instrumentation and Control Safety Systems NRC Review of Framatome TXS-Compact Topical Report RA-24-0031, Annual Radiological Environmental Operating Report - 20232024-04-23023 April 2024 Annual Radiological Environmental Operating Report - 2023 RA-24-0103, Response to Request for Additional Information (RAI) Regarding License Amendment Request for a One-Time Extension to the Integrated Leak Rate Test Interval2024-04-19019 April 2024 Response to Request for Additional Information (RAI) Regarding License Amendment Request for a One-Time Extension to the Integrated Leak Rate Test Interval RA-24-0094, Request for Approval of Duke Energy Corporation Transition to ANSI/ANS3.1-2014, American National Standard for Selection and Training of Nuclear Power Plant Personnel and Revision 4 of Regulatory Guide 1.8, Rev. 4 Qualification and Traini2024-04-17017 April 2024 Request for Approval of Duke Energy Corporation Transition to ANSI/ANS3.1-2014, American National Standard for Selection and Training of Nuclear Power Plant Personnel and Revision 4 of Regulatory Guide 1.8, Rev. 4 Qualification and Training RA-24-0101, (Mns), Units 1 and 2, Notification of Deviation from MRP-227, Revision 1-A Baffle-to-Former Bolt Inspection Frequency2024-04-16016 April 2024 (Mns), Units 1 and 2, Notification of Deviation from MRP-227, Revision 1-A Baffle-to-Former Bolt Inspection Frequency RA-24-0093, Response to NRC Regulatory Issue Summary 2024-01 Preparation and Scheduling of Operator Licensing Examinations2024-04-0202 April 2024 Response to NRC Regulatory Issue Summary 2024-01 Preparation and Scheduling of Operator Licensing Examinations RA-24-0086, 10 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums2024-04-0101 April 2024 10 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums RA-24-0085, Onsite Property Insurance Coverage2024-04-0101 April 2024 Onsite Property Insurance Coverage RA-24-0082, Core Operating Limits Report (COLR) for Unit 2 Cycle 27 Reload Core2024-03-21021 March 2024 Core Operating Limits Report (COLR) for Unit 2 Cycle 27 Reload Core RA-24-0073, Transmittal of Oconee Unit 2, Refuel 31 (O2R31) Inservice Inspection (ISI) Report, Fifth 10-Year ISI Interval2024-03-21021 March 2024 Transmittal of Oconee Unit 2, Refuel 31 (O2R31) Inservice Inspection (ISI) Report, Fifth 10-Year ISI Interval RA-24-0068, Condition Prohibited by Technical Specifications and Loss of Safety Function Due to Failed Damper Controller for the 2A1 Emergency Diesel Generator Room Ventilation Fan2024-03-0404 March 2024 Condition Prohibited by Technical Specifications and Loss of Safety Function Due to Failed Damper Controller for the 2A1 Emergency Diesel Generator Room Ventilation Fan RA-24-0067, Independent Spent Fuel Storage Installation (ISFSI)2024-02-29029 February 2024 Independent Spent Fuel Storage Installation (ISFSI) RA-24-0071, Passive Containment Isolation Device Inoperability Results in Operation or Condition Prohibited by Technical Specifications2024-02-29029 February 2024 Passive Containment Isolation Device Inoperability Results in Operation or Condition Prohibited by Technical Specifications RA-24-0072, Inappropriate Procedural Guidance for Planned Online Maintenance Results in Event or Condition That Could Have Prevented Fulfillment of a Safety Function Licensee2024-02-29029 February 2024 Inappropriate Procedural Guidance for Planned Online Maintenance Results in Event or Condition That Could Have Prevented Fulfillment of a Safety Function Licensee RA-24-0004, End of Cycle 29 (M1R29) Inservice Inspection Summary Report2024-02-21021 February 2024 End of Cycle 29 (M1R29) Inservice Inspection Summary Report RA-24-0053, Registration for Use of General License Spent Fuel Cask Number 1762024-02-20020 February 2024 Registration for Use of General License Spent Fuel Cask Number 176 RA-23-0242, Proposed Alternative for the Inspection of Reactor Vessel Closure Head Penetrations in Accordance with 10 CFR 50.55a(z)(2)2024-01-10010 January 2024 Proposed Alternative for the Inspection of Reactor Vessel Closure Head Penetrations in Accordance with 10 CFR 50.55a(z)(2) RA-23-0325, Submittal of Procedures CSD-EP-HNP-0101-01, 02, CSD-EP-ONS-0101-01, CSD-EP-RNP-0101-01, and EP-RNP-EPLAN-ANNEX2024-01-0808 January 2024 Submittal of Procedures CSD-EP-HNP-0101-01, 02, CSD-EP-ONS-0101-01, CSD-EP-RNP-0101-01, and EP-RNP-EPLAN-ANNEX RA-23-0295, Delay of Planned End Date for Fourth 10-Year Inservice Testing (1ST) Program Interval2024-01-0404 January 2024 Delay of Planned End Date for Fourth 10-Year Inservice Testing (1ST) Program Interval RA-23-0320, Notification of Deviation from MRP-227, Revision 1-A Baffle-to-Former Bolt Inspection Frequency2023-12-14014 December 2023 Notification of Deviation from MRP-227, Revision 1-A Baffle-to-Former Bolt Inspection Frequency RA-23-0306, Procedures CSD-EP-BNP-0101-01, EAL Technical Basis Document, Revision 006 and CSD-EP-CNS-0101-01, EAL Technical Basis Document, Revision 005, Summary Of.2023-12-12012 December 2023 Procedures CSD-EP-BNP-0101-01, EAL Technical Basis Document, Revision 006 and CSD-EP-CNS-0101-01, EAL Technical Basis Document, Revision 005, Summary Of. RA-23-0318, Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-0404 December 2023 Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation RA-23-0284, RA-23-0284 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-16016 November 2023 RA-23-0284 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation RA-23-0182, Duke Energy Carolinas, LLC - License Amendment Request to Revise Technical Specification 5.5.2, Containment Leakage Rate Testing Program for a One-Time Extension of the Units 1, 2 and 3 Type a Leak Rate Test Frequency2023-11-16016 November 2023 Duke Energy Carolinas, LLC - License Amendment Request to Revise Technical Specification 5.5.2, Containment Leakage Rate Testing Program for a One-Time Extension of the Units 1, 2 and 3 Type a Leak Rate Test Frequency RA-23-0288, End of Cycle 27 (C1 R27) Steam Generator Tube Inspection Report2023-11-16016 November 2023 End of Cycle 27 (C1 R27) Steam Generator Tube Inspection Report RA-23-0304, Transmittal of Core Operating Limits Report (COLR) for Oconee Unit 2 Cycle 32 (Revision 0)2023-11-14014 November 2023 Transmittal of Core Operating Limits Report (COLR) for Oconee Unit 2 Cycle 32 (Revision 0) RA-23-0279, Supplement to Application to Adopt Risk-Informed Completion Times TSTF-505, Revision 2 and Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power2023-11-0202 November 2023 Supplement to Application to Adopt Risk-Informed Completion Times TSTF-505, Revision 2 and Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power 2024-09-30
[Table view] Category:Quality Assurance Program
MONTHYEARRA-19-0115, Transmittal of the Duke Energy Corporation Topic Report (Duke QAPD-001-A), Amendment 442019-02-18018 February 2019 Transmittal of the Duke Energy Corporation Topic Report (Duke QAPD-001-A), Amendment 44 RA-18-0004, Duke Energy Transmittal of Topical Report DUKE-QAPD-001-A, Amendment 432018-08-13013 August 2018 Duke Energy Transmittal of Topical Report DUKE-QAPD-001-A, Amendment 43 RA-17-0025, Transmittal of the Duke Energy Corporation Topical Report (Duke-QAPD-001-A), Amendment 422017-05-22022 May 2017 Transmittal of the Duke Energy Corporation Topical Report (Duke-QAPD-001-A), Amendment 42 RA-15-0050, Implementation of a Duke Energy Common Quality Assurance Topical Report2016-01-19019 January 2016 Implementation of a Duke Energy Common Quality Assurance Topical Report ML15238A9002015-08-12012 August 2015 CISI-1462.10.0040, Revision 0, Fourth Interval Inservice Inspection Outage Schedule, Quality Assurance Program Related RA-14-0021, Change to Quality Assurance Topical Report, Amendment 402014-10-23023 October 2014 Change to Quality Assurance Topical Report, Amendment 40 ML13303B5242013-10-0707 October 2013 Duke Energy Carolinas, LLC - Quality Assurance Program Topical Report Amendment 40 ML11304A1352011-10-26026 October 2011 Independent Spent Fuel Storage Installation, Quality Assurance Program Topical Report Amendment 39 ML1021102942010-07-28028 July 2010 ISFSI, McGuire Units 1 & 2, Catawba Units 1 & 2, Quality Assurance Program Topical Report Alternate Amendment 37 ML1006103812010-02-18018 February 2010 Duke Energy Carolinas, Topical Report Quality Assurance Program, Revision 37 ML0912605562009-04-20020 April 2009 Request for Quality Assurance Program Approval for Radioactive Material Packages No. 0266 ML0830900492008-10-23023 October 2008 Duke Energy Carolinas Topical Report, Quality Assurance Program, Revision 36 ML0725407962007-08-30030 August 2007 Duke Energy Carolinas Topical Report Quality Assurance Program ML0613603572006-05-0404 May 2006 Duke Power Company, Transmittal of QA Topical Report, Revision 34 ML0612902942006-05-0202 May 2006 Units 1 & 2, Quality Assurance Program Amendment 34 ML0422302072004-08-0202 August 2004 Duke Energy Corp Topical Report, Quality Assurance Program, Revision 33 - Catawba, McGuire & Oconee Nuclear Station ML0421903532004-07-30030 July 2004 Summary of 07/27/2004 Meeting with Duke Energy Corp. Re. Modification to Quality Assurance Program for Catawba, McGuire, and Oconee Nuclear Station, Attachment 2 - Meeting Handouts ML0417407192004-06-10010 June 2004 Duke Power Company, Quality Assurance Program Topical Report, Revision 32 ML0416103902004-06-0303 June 2004 Units, 1, 2 and 3, McGuire, Units 1 and 2 and Catawba, Units 1 and 2, Alternative Submittal of Duke Energy Topical Report, Duke-1-A, Amendment 32 ML0301600572002-12-31031 December 2002 Amendment 31 to Duke Energy Topical Report Quality Assurance Program ML0236101412002-12-18018 December 2002 Duke Energy Corporation, Nuclear Quality Assurance Program Amendment 32 ML0236004972002-12-16016 December 2002 Amendment 31 to the Duke Energy Corp., Topical Report, Duke-1-A, Quality Assurance Program ML0222701742002-08-0202 August 2002 Duke Power Company Topical Report Quality Assurance Program ML0222701552002-07-31031 July 2002 Duke Energy Corp., Amendment 30 to Topical Report, Duke-1-A, Quality Assurance Program for Oconee, McGuire & Catawba Nuclear Stations 2019-02-18
[Table view] Category:Topical Report
MONTHYEARRA-20-0317, Review Request for the Aging Management Program and Inspection Plan for the Catawba Nuclear Station Units 1 and 2 Reactor Vessel Internals to Implement MRP-227, Revision 1-A2020-10-15015 October 2020 Review Request for the Aging Management Program and Inspection Plan for the Catawba Nuclear Station Units 1 and 2 Reactor Vessel Internals to Implement MRP-227, Revision 1-A RA-19-0115, Transmittal of the Duke Energy Corporation Topic Report (Duke QAPD-001-A), Amendment 442019-02-18018 February 2019 Transmittal of the Duke Energy Corporation Topic Report (Duke QAPD-001-A), Amendment 44 RA-18-0004, Duke Energy Transmittal of Topical Report DUKE-QAPD-001-A, Amendment 432018-08-13013 August 2018 Duke Energy Transmittal of Topical Report DUKE-QAPD-001-A, Amendment 43 ML17356A1782017-12-13013 December 2017 Attachment 1: WCAP-18265-NP, Rev. 0, Aging Management Program and Inspection Plan for the McGuire Nuclear Station Units 1 & 2 Reactor Vessel Internals. RA-17-0025, Transmittal of the Duke Energy Corporation Topical Report (Duke-QAPD-001-A), Amendment 422017-05-22022 May 2017 Transmittal of the Duke Energy Corporation Topical Report (Duke-QAPD-001-A), Amendment 42 RA-15-0050, Implementation of a Duke Energy Common Quality Assurance Topical Report2016-01-19019 January 2016 Implementation of a Duke Energy Common Quality Assurance Topical Report CNS-15-078, WCAP-18060-NP, Revision 1, Response to RAIs Concerning the Use of RAPTOR-M3G for the Catawba Unit 1 Measurement Uncertainty Recapture (Mur) Power Uprate Fluence Evaluations2015-11-30030 November 2015 WCAP-18060-NP, Revision 1, Response to RAIs Concerning the Use of RAPTOR-M3G for the Catawba Unit 1 Measurement Uncertainty Recapture (Mur) Power Uprate Fluence Evaluations CNS-15-024, WCAP-17993-NP, Revision 0-B, Justification for the Use of RAPTOR-M3G for the Catawba, Unit 1, Measurement Uncertainty Recapture (Mur) Power Uprate Fluence Evaluations.2015-04-23023 April 2015 WCAP-17993-NP, Revision 0-B, Justification for the Use of RAPTOR-M3G for the Catawba, Unit 1, Measurement Uncertainty Recapture (Mur) Power Uprate Fluence Evaluations. RA-14-0021, Change to Quality Assurance Topical Report, Amendment 402014-10-23023 October 2014 Change to Quality Assurance Topical Report, Amendment 40 ML13305A1212013-09-30030 September 2013 ANP-3127, Revision 2, Pressure-Temperature Limits at 54 EFPY, Enclosure 1 ML13058A0602012-02-22022 February 2012 Areva, Topical Report ANP-3127, Rev. 1, Oconee Nulcear Station, Units 1, 2 & 3, Pressure-Temperature Limits at 54 EFPY ML11304A1352011-10-26026 October 2011 Independent Spent Fuel Storage Installation, Quality Assurance Program Topical Report Amendment 39 ML1021102942010-07-28028 July 2010 ISFSI, McGuire Units 1 & 2, Catawba Units 1 & 2, Quality Assurance Program Topical Report Alternate Amendment 37 ML1006103812010-02-18018 February 2010 Duke Energy Carolinas, Topical Report Quality Assurance Program, Revision 37 ML0830900492008-10-23023 October 2008 Duke Energy Carolinas Topical Report, Quality Assurance Program, Revision 36 ML0725407962007-08-30030 August 2007 Duke Energy Carolinas Topical Report Quality Assurance Program ML0613603572006-05-0404 May 2006 Duke Power Company, Transmittal of QA Topical Report, Revision 34 ML0517401562005-05-31031 May 2005 DPC-NE-3005-A, Revision 2, Oconee Nuclear Station, UFSAR Chapter 15 Transient Analysis Methodology. ML0503200312004-09-30030 September 2004 DPC-NE-3003-A, Revision 1, Mass and Energy Release and Containment Response Methodology. ML0506803092004-09-30030 September 2004 DPC-NE-3000-A, Rev 3, Thermal-Hydraulic Transient Analysis Methodology. ML0510103212004-08-31031 August 2004 Non-proprietary Nuclear Design Methodology Using CASMO-4 / SIMULATE-3 MOX, DPC-NE-1005-NP-A, Revision 0 ML0423902142004-08-20020 August 2004 Westinghouse Owners Group Request to Withdraw WCAP-16168-NP, Risk-Informed Extension of Reactor Vessel In-Service Inspection Interval, (PA-MSC-0120) ML0422302072004-08-0202 August 2004 Duke Energy Corp Topical Report, Quality Assurance Program, Revision 33 - Catawba, McGuire & Oconee Nuclear Station ML0421903532004-07-30030 July 2004 Summary of 07/27/2004 Meeting with Duke Energy Corp. Re. Modification to Quality Assurance Program for Catawba, McGuire, and Oconee Nuclear Station, Attachment 2 - Meeting Handouts ML0417407192004-06-10010 June 2004 Duke Power Company, Quality Assurance Program Topical Report, Revision 32 ML0416103902004-06-0303 June 2004 Units, 1, 2 and 3, McGuire, Units 1 and 2 and Catawba, Units 1 and 2, Alternative Submittal of Duke Energy Topical Report, Duke-1-A, Amendment 32 ML0402600162004-01-19019 January 2004 Request for Review of BAW-2441, Revision 2, Risk Informed Justification for LCO End-State Changes. ML0332302252003-11-12012 November 2003 Submittal of WCAP-16084-NP, Development of Risk-Informed Safety Analysis Approach and Pilot Application. ML0331100912003-10-23023 October 2003 Submittal of Revision 3 to Ice Condenser Utility Group Topical Report No. ICUG-001: Application of the Active Ice Mass Management Concept to the Ice Condenser Ice Mass Technical Specification ML0319206472003-06-19019 June 2003 to Ice Condenser Utility Group Topical Report No. ICUG-001: Application of the Active Ice Mass Management Concept to the Ice Condenser Ice Mass Technical Specification ML0323405632003-05-29029 May 2003 Draft Revision 2 to Ice Condenser Utility Group Topical Report No. ICUG-001: Application of the Active Ice Mass Management Concept to the Ice Condenser Ice Mass Technical Specification ML0314904692003-03-21021 March 2003 Revisions to Topical Reports DPC-NE-3000 and 3005 in Support of Steam Generator Replacement Response to NRC Staff Request for Additional Information ML0305705032003-02-19019 February 2003 Issuance of Approved Version of Topical Report DPC-NE-2009A, Revision 2, Duke Power Westinghouse Fuel Transition Report, Table of Contents - Attachment B, Chapter 6 ML0305705352003-02-19019 February 2003 Issuance of Approved Version of Topical Report DPC-NE-2009A, Revision 2, Duke Power Westinghouse Fuel Transition Report, Section E, Table of Contents - References ML0305902512003-02-13013 February 2003 Submittal of Published Versions of Approved Topical Reports, Table of Contents - Safety Evaluation ML0305901742003-02-13013 February 2003 Submittal of Published Versions of Approved Topical Reports, Table of Contents - Section 11 ML0305902452003-02-13013 February 2003 Submittal of Published Versions of Approved Topical Reports, Section 12 - Safety Evaluation Report ML0305903242003-02-13013 February 2003 Submittal of Published Versions of Approved Topical Reports, Table of Contents - Safety Evaluation ML0301600572002-12-31031 December 2002 Amendment 31 to Duke Energy Topical Report Quality Assurance Program ML0236004972002-12-16016 December 2002 Amendment 31 to the Duke Energy Corp., Topical Report, Duke-1-A, Quality Assurance Program ML0230902522002-09-16016 September 2002 Non-Proprietary Approved Version of Topical Report DPC-NE-2005A, Revision 3, Duke Power Company Thermal-Hydraulic Statistical Core Design Methodology, Appendix a, Revision 0 - Appendix E, Attachment 2 ML0230902992002-09-16016 September 2002 Non-Proprietary Approved Version of Topical Report DPC-NE-2005A, Revision 3, Duke Power Company Thermal Hydraulic Statistical Core Design Methodology - Table A-4 ML0222701742002-08-0202 August 2002 Duke Power Company Topical Report Quality Assurance Program ML0220702482002-07-26026 July 2002 Request for Additional Information - Review of Duke Topical Report DPC-NE-2009, Revision 2 ML0217102582002-06-13013 June 2002 Transmittal of Revisions to Topical Reports DPC-NE-3000, -3003, & 3005 in Support of Steam Generator Replacement ML0208705322002-03-19019 March 2002 Reactor Cavity Neutron Measurement Program ML0208006742002-02-28028 February 2002 Stations, Topical Report DPC-NE-2009 (TAC Nos. MA2359, MA2361, MA2411, MA2412), Revision 2 - Updates to Chapters 2, 4 & 5 2020-10-15
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Text
DUKE ENERGY.so, Ernest J. Kapopoulos,Jr.
s ,
526 South Church Street Charlotte,NC 28202 MailingAddress:
Mail Code ECO7H/P.O. Box 1006 Charlotte, NC 28201-1006 704-382-8162 704-382-4541 fax October 23, 2014 10 CFR 50.54(a)(4)
RA-1 4-0021 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Catawba Nuclear Station, Unit Nos. 1 and 2 Docket Nos. 50-413 and 50-414/ Renewed License Nos. NPF-35 and NPF-52 McGuire Nuclear Station, Unit Nos. 1 and 2 Docket Nos. 50-369 and 50-370/ Renewed License Nos. NPF-9 and NPF- 17 Oconee Nuclear Station, Unit Nos. 1, 2 and 3 Docket Nos. 50-269, 50-270, 50-287 / Renewed License Nos. DPR-38, DPR-47, and DPR-55
Subject:
Change to Quality Assurance Topical Report, Amendment 40
Reference:
Letter from NIRMA (Linda Torunski) to USNRC (Eric J. Leeds, et al.), "Regulatory Information Summary 00-18, "Guidance on the Management of Quality Assurance Records on Electronic Media," dated July 7, 2011 (ML11200A122)
Duke Energy Carolinas (DEC) is submitting the following change to their Quality Assurance Topical Report (QATR). These changes are submitted for approval by the Nuclear Regulatory Commission (NRC) in accordance with 10 CFR 50.54(a)(4).
The change:
Change the following portions of Table 17-1, "Conformance of DEC's Program to Quality Assurance Standards, Requirements, and Guides," under the description of Regulatory Guide 1.88 Rev 2 - Collection, Storage, and Maintenance of Nuclear Power Plant Quality Assurance Records (pages 17-8 and 17-9):
Delete the following portion:
The DEC program for storage of records on optical disks meets the quality controls contained in NRC Generic Letter 88-18.
DEC fully meets [Nuclear Information and Records Management Association] NIRMA Technical Guide (TG) 11-1998, Authentication of Records and Media, NIRMA TG 15-1998, "Management of Electronic Records," and NIRMA TG 16-1998, "Software Configuration Management and Quality Assurance" for managing quality assurance records in electronic media:
U.S. Nuclear Regulatory Commission October 23, 2014 Page 2 NIRMA TG 21-1998, "Electronic Records Protection and Restoration" - The data backup provisions in sections 5.4.2 and 5.4.4 are not being fully met. Until the backup requirements are met, dual storage or microfilm will be used for all QA Records And replace with the following:
The DEC program for storage of records on microfilm, dual storage or in electronic format meets the preservation requirement for the retention of [Quality Assurance] QA Records.
For management of electronic records, DEC uses the following:
- NIRMA TG 11-2011 "Authentication of Records and Media"
- NIRMA TG 15-2011, "Management of Electronic Records,"
- NIRMA TG 16-2011, "Software Quality Assurance Documentation and Records"
- NIRMA TG 21-2011, "Required Records Protection, Disaster Recovery and Business Continuation" Reason for the change:
DEC record media for long term storage has typically been microfilm, with some records being maintained electronically. All DEC Plants have the option in their QATR to maintain electronic records in accordance with Generic Letter 88-18, "Plant Record Storage on Optical Disks," and RIS 2000-18, "Guidance on Managing Quality Assurance Records in Electronic Media," with 1998 NIRMA TGs. RIS 2000-18 was a significant development for the industry and is the basis for managing electronic records at many of the legacy U.S. nuclear power plants, as well as with new nuclear plant construction. The RIS endorsed the additional guidance needed in the industry to establish adequate programmatic controls in this new environment. As such, the standards it endorsed are currently included in the DEC QATR. However, since RIS 2000-18 refers specifically to the 1998 versions of the NIRMA TGs, DEC interprets that they are limited to the guidance provided in the 1998 versions of the TGs. Therefore, our program is limited to using outdated philosophies, perspectives, and guidance from the early- to mid-1990s rather than fully implementing an integrated approach for records management. This change will allow DEC to use the latest available NIRMA records standards.
Basis for the change:
Criterion XVII of 10 CFR Part 50 Appendix B, Quality Assurance Records, specifies, "Sufficient records shall be maintained to furnish evidence of activities affecting quality. The records shall include at least the following: Operating logs and the results of reviews, inspections, tests, audits, monitoring of work performance, and materials analyses. The records shall also include closely-related data such as qualifications of personnel, procedures, and equipment. Inspection and test records shall, as a minimum, identify the inspector or data recorder, the type of observation, the results, the acceptability, and the action taken in connection with any deficiencies noted. Records shall be identifiable and retrievable. Consistent with applicable regulatory requirements, the applicant shall establish requirements concerning record retention, such as duration, location, and assigned responsibility."
U.S. Nuclear Regulatory Commission October 23, 2014 Page 3 Regulatory Guide 1.88, "Requirements for Collection ,Storage, and Maintenance of Quality Assurance Records for Nuclear Power Plants," Rev. 2 incorporates ANSI N45.2.9-1974. On October 23, 2000, the NRC issued a Regulatory Issue Summary (RIS) 2000-18, "Guidance on Management of Quality Assurance Records in Electronic Media," to address the management of electronic records in support of Quality Assurance requirements for nuclear facilities. The guidance can also be applied to the record keeping and maintenance requirements present in other parts of the regulations that specify that storing records in the form of electronic media is acceptable. RIS 2000-18 refers to the 1998 revisions of the following NIRMA TGs:
- NIRMA TG-1 1, "Authentication of Records and Media"
- NIRMA TG-15, "Management of Electronic Records"
- NIRMA TG-16, "Software Configuration Management and Quality Assurance"
- NIRMA TG-21, "Required Records Protection and Restoration" The TGs listed have undergone numerous changes since the publication of RIS 2000-18, with the most current revisions of all four being approved by NIRMA in 2011. The 2011 revisions reflect changes in electronic records best practices and evolved technology.
This issue directly affects not only the legacy reactor sites, but also those firms that are embarking on new plant construction. The new construction projects are striving to embrace new methods and technologies in records and information management (RIM) by attempting complete electronic integration of the entire lifecycle of records to ultimately provide traceability from beginning to end. This includes:
- Early Site Permit/Combined Operating License (ESP/COL) submittals to the USNRC,
- Handover exchange of documents, data, and information between firms during:
o design and construction, o pre-operational startup testing, o turnover of baseline as-built information (documents, data, and records) as they enter the operations and maintenance phase.
- Being accessible and useful per state, federal, nuclear insurance and other requirements during the plant's operating life, including decommissioning.
Improvements in electronic record keeping need to be addressed in current terms. Because the 1998 TGs were developed before currently available technology existed, they do not address the new issues and concerns and/or considerations that must be taken into account in order for the proper advances to be embraced. Without using the information provided by the updated TGs, complete electronic integration becomes stagnant.
Due to the ever-changing technology environment, the lessons learned throughout the industry, and evolution of various technologies including enterprise content management (ECM) since the 1990s, NIRMA has continued to update each of the aforementioned TGs. The latest 2011 TGs represent a "best of class" perspective on the use of electronic information technologies for document control, records management, and data administration, while continuing to comply with the various federal and state regulations, and other legal and business requirements.
U.S. Nuclear Regulatory Commission October 23, 2014 Page 4 The context for the 1998 versions was the nuclear records management approaches and information technologies present in the mid-1 990s, consisting primarily of image-capture based systems (scanned documents resulting in single- or multi-page TIF images). These images were typically captured to optical disks, which were managed in multi-platter "jukeboxes," and accessed through client-server, LAN-based networks. The 1998 versions recognized the need to expand beyond optical disk storage systems into magnetic disk storage, and address electronic record formats that can be viewed over time. The 1998 versions also brought to light the need to formally address software configuration management and quality assurance, since it was recognized that licensees would become dependent on the electronic record-only viewable, not as paper, but through the means of information technology (hardware and software). This dependency also dictated the need to address electronic records protection, backups, and disaster recovery, to be compliant with regulatory requirements.
The 2011 TG versions retain the fundamental philosophies of the 1998 versions and maintain the relationship among the four stated TGs, i.e., TG-15 presents the over-arching program for managing electronic records, with TG's 11, 16, and 21 providing more detailed information into specific areas of records authentication, software quality assurance, and disaster recovery, respectively. The key changes are based on development and implementation of enterprise content management systems, web-based technologies, and higher capacity LAN/WAN networks. Leveraging those technologies enabled the development of more efficient and effective best practices for managing electronic records, with authentication and records turnover occurring more frequently in "e-space." The 2011 versions are written in anticipation of wider use of information technologies at the nuclear facilities, and the ever-present need to achieve integration of information to support plant operations and decision-making.
The referenced letter provides a high level comparison of the 1998 version of the TGs versus the recent updates.
The proposed change will remain in compliance with Criterion XVII by continuing to directly impose the requirements of Appendix B. The change will enhance compliance by allowing use of the latest best practices and evolved technology for QA records management.
A markup of the QATR pages affected by this change is included as Attachment 1. Clean typed pages are provided as Attachment 2.
Should you have any questions regarding this request, please contact Julie Olivier at (980) 373-4045.
Sincerely, Ernest J. Kapopoulos, Jr.
Vice President CorporateGovernance and OperationsSupport Attachments:
- 1. Quality Assurance Topical Report Pages 17-8 and 17-9 with Requested Change
- 2. Clean Typed Quality Assurance Topical Report Pages 17-8 and 17-9
U.S. Nuclear Regulatory Commission October 23, 2014 Page 5 xc:
V. M. McCree, Region IIAdministrator U.S. Nuclear Regulatory Commission Marquis One Tower 245 Peachtree Center Avenue NE, Suite 1200 Atlanta, Georgia 30303-1257 Randy Hall, Project Manager (ONS)
U.S. Nuclear Regulatory Commission 11555 Rockville Pike Rockville, MD 20852-2738 G. E. Miller, Project Manager (CNS and MNS)
U.S. Nuclear Regulatory Commission 11555 Rockville Pike Rockville, MD 20852-2738 USNRC Resident Inspector - CNS USNRC Resident Inspector - MNS USNRC Resident Inspector - ONS
U.S. Nuclear Regulatory Commission October 23, 2014 Page 6 bxc:
Chris Nolan Toni Pasour (For CNS Licensing/Nuclear Records)
Randy Hart Kay Crane (For MNS Licensing/Nuclear Records)
Jeff Robertson Judy Smith (For ONS Licensing/Nuclear Records)
Chris Wasik NCMPA-1 PMPA NCEMC ONS Master File - ON02DM (File OS 801.01)
MNS Master File - MG02DM (File MC 801.01)
CNS Master File - CN04DM (File CN 801.01)
RGC Date File- CN01 RC ELL File: (Corporate)
RA-14-0021 Attachment 1 Quality Assurance Topical Report Pages 17-8 and 17-9 with Requested Change 3 Pages Follow
Table 17-1 Conformance of DEC's Program to Quality Assurance Standards, Requirements and Guides Standard, Requirement or Guide Conformance Remarks Status Assurance Requirements for Design of Clarification the originator's immediate supervisor for design verification shall Nuclear Power Plants be restricted to special situations where the immediate supervisor is the only individual capable of performing the verification.
Advance justification for such use shall be documented and signed by the supervisor's management. And the frequency and effectiveness of the supervisor's use as design verifier are independently verified to guard against abuse. The supervisor will not be the design verifier on work for which he is the actual performer / originator.
Regulatory Guide 1.74 Rev (0) - Quality Conforms RG 1.74 Rev (0) Incorporates ANSI N45.2.10-1973. Some Assurance Terms and Definitions definitions used by DEC are worded differently than those in this standard; however, the general meanings are the same.
Regulatory Guide 1.88 Rev (2) - Collection, Alternative RG 1.88 Rev (2) Incorporates ANSI N45.2.9-1974. The DEC Storage, and Maintenance of Nuclear QAP conforms to RG 1.88 except the records storage facilities Power Plant Quality Assurance Records have a minimum 3-hour rating. A qualified Fire Protection Engineer will evaluate record storage areas (including satellite files) to assure records are adequately protected from damage.
The fire protection engineer shall be a graduate of an engineering curriculum of accepted standing and shall have completed not less than 6 years of engineering attainment indicative of growth in engineering competency and achievement, 3 years of which shall have been in responsible charge of fire protection engineering work. The DEC progrFam F .t..ag.of .e.e.d, on optical d*c*,
meets the quality cOtRole6 onAinoAd- in N'RC- Genric*Letter 88 18.
DECr f'!y meets NIRM.:.T,.hni*ca Guide /TtG_ 4 4 4108, Replace strikethrough with Insert A AuthenticAt of Recordc 2nd Modia, NIRMA TO 15 1008, "Management of El!ectFroic Recrede," and NIRA.AA. TO 16 00, 22ISofTtar-e Configuration Management and Qualit',' A*cuanca*" for managing quality ascrUanca Focards in electronic modia:
NURA&A TGn f2-11--4008, "Elect. -A*r-.i IR-Aeaprd- Protectpion and 17-8 Amendment 40
Table 17-1 Conformance of DEC's Program to Quality Assurance Standards, Requirements and Guides Standard, Requirement or Guide Conformance Remarks Status Restorfation" The data backup priinsn ections 5.4.2 and
.4.4 a-r no*t be;ng fully met. Until the chk-Up ro;qui-emonts are met, dual Storage or micrafilim ywill..
be used for all QA RecorFds.
Regulatory Guide 1.94 Rev (1) - Quality for Alternative RG 1.94 Rev (1) Incorporates ANSI program for McGuire and Installation, Inspection, and Testing of Catawba conforms to ANSI N45.2.5-1974 except the length of Structural Concrete and Structural Steel bolts shall be flush with the outside face of the nut.
During the Construction Phase of Nuclear Paragraph 5.5 requires inspection of structural steel welding to be Power Plants performed in accordance with the provisions of Section 6 of the AWS D1.1. Visual Weld Acceptance Criteria (VWAC) for Structural Welding at Nuclear Power Plants, NCIG-01, Revision 2, prepared by the Nuclear Construction Issues Group (NCIG) and accepted by the NRC in their letter to the NCIG dated June 26, 1985 may be used as an alternative to AWSD1.1 for non ASME Code structural weld inspections. (July 31, 2000 J M Farley SER)
Regulatory Guide 1.116 Rev (0-R) - Quality Conforms RG 1.116 Rev (0-R) Incorporates ANSI N45.2.8-1975 Assurance Requirements for Installation, Inspections, and Testing of Mechanical Equipment and Systems Regulatory Guide 1.123 Rev (1) - Quality Alternative RG 1.123 Rev (1) Incorporates ANSI N45.2.13-1976. With Assurance Requirements for control of respect to ANSI N45.2.13, Section 3.2, "Content of the Procurement of Items and Services for Procurement Documents," Subsection 3.2.3, "QAP Requirement,"
Nuclear Plants DEC takes the following exception: When purchasing commercial-grade calibration services from calibration laboratories accredited by a nationally recognized accrediting body, the procurement documents are not required to impose a QAP consistent with ANSI N45.2-1977. Nationally-recognized accrediting bodies include the National Voluntary Laboratory Accreditation Program (NVLAP) administered by the National Institute of Standards and Technology (NIST) and other accrediting bodies recognized by NVLAP via a Mutual Recognition Arrangement (MRA). In such cases, accreditation Amendment 40 17-9
QATR Insert A:
The DEC program for storage of records on microfilm, dual storage or in electronic format meets the preservation requirement for the retention of CIA Records.
For management of electronic records, DEC uses the following standards:
- NIRMA TG 11-2011 "Authentication of Records and Media"
- NIRMA TG 15-2011, "Management of Electronic Records,"
- NIRMA TG 16-2011, "Software Quality Assurance Documentation and Records"
- NIRMA TG 21-2011, "Required Records Protection, Disaster Recovery and Business Continuation"
RA- 14-0021 Attachment 2 Clean Typed Quality Assurance Topical Report Pages 17-8 and 17-9 2 Pages Follow
Table 17-1 Conformance of DEC's Program to Quality Assurance Standards, Requirements and Guides Standard, Requirement or Guide Conformance Remarks Status Assurance Requirements for Design of Clarification the originator's immediate supervisor for design verification shall Nuclear Power Plants be restricted to special situations where the immediate supervisor is the only individual capable of performing the verification.
Advance justification for such use shall be documented and signed by the supervisor's management. And the frequency and effectiveness of the supervisor's use as design verifier are independently verified to guard against abuse. The supervisor will not be the design verifier on work for which he is the actual performer / originator.
Regulatory Guide 1.74 Rev (0) - Quality Conforms RG 1.74 Rev (0) Incorporates ANSI N45.2.10-1973. Some Assurance Terms and Definitions definitions used by DEC are worded differently than those in this standard; however, the general meanings are the same.
Regulatory Guide 1.88 Rev (2) - Collection, Alternative RG 1.88 Rev (2) Incorporates ANSI N45.2.9-1974. The DEC Storage, and Maintenance of Nuclear QAP conforms to RG 1.88 except the records storage facilities Power Plant Quality Assurance Records have a minimum 3-hour rating. A qualified Fire Protection Engineer will evaluate record storage areas (including satellite files) to assure records are adequately protected from damage.
The fire protection engineer shall be a graduate of an engineering curriculum of accepted standing and shall have completed not less than 6 years of engineering attainment indicative of growth in engineering competency and achievement, 3 years of which shall have been in responsible charge of fire protection engineering work. The DEC program for storage of records on microfilm, dual storage or in electronic format meets the preservation requirement for the retention of QA Records.
For management of electronic records, DEC uses the following standards:
- NIRMA TG 11-2011 "Authentication of Records and Media"
- NIRMA TG 15-2011, "Management of Electronic Records,"
- NIRMA TG 16-2011, "Software Quality Assurance 17-8 Amendment
Table 17-1 Conformance of DEC's Program to Quality Assurance Standards, Requirements and Guides Standard, Requirement or Guide Conformance Remarks Status Documentation and Records"
- NIRMA TG 21-2011, "Required Records Protection, Disaster Recovery and Business Continuation" Regulatory Guide 1.94 Rev (1) - Quality for Alternative RG 1.94 Rev (1) Incorporates ANSI program for McGuire and Installation, Inspection, and Testing of Catawba conforms to ANSI N45.2.5-1974 except the length of Structural Concrete and Structural Steel bolts shall be flush with the outside face of the nut.
During the Construction Phase of Nuclear Paragraph 5.5 requires inspection of structural steel welding to be Power Plants performed in accordance with the provisions of Section 6 of the AWS D1.1. Visual Weld Acceptance Criteria (VWAC) for Structural Welding at Nuclear Power Plants, NCIG-01, Revision 2, prepared by the Nuclear Construction Issues Group (NCIG) and accepted by the NRC in their letter to the NCIG dated June 26, 1985 may be used as an alternative to AWSD1.1 for non ASME Code structural weld inspections. (July 31, 2000 J M Farley SER)
Regulatory Guide 1.116 Rev (0-R) -Quality Conforms RG 1.116 Rev (0-R) Incorporates ANSI N45.2.8-1975 Assurance Requirements for Installation, Inspections, and Testing of Mechanical Equipment and Systems Regulatory Guide 1.123 Rev (1) - Quality Alternative RG 1.123 Rev (1) Incorporates ANSI N45.2.13-1976. With Assurance Requirements for control of respect to ANSI N45.2.13, Section 3.2, "Content of the Procurement of Items and Services for Procurement Documents," Subsection 3.2.3, "QAP Requirement,"
Nuclear Plants DEC takes the following exception: When purchasing commercial-grade calibration services from calibration laboratories accredited by a nationally recognized accrediting body, the procurement documents are not required to impose a QAP consistent with ANSI N45.2-1977. Nationally-recognized accrediting bodies include the National Voluntary Laboratory Accreditation Program (NVLAP) administered by the National Institute of Standards and Technology (NIST) and other accrediting bodies recognized by NVLAP via a Mutual Recognition Arrangement (MRA). In such cases, accreditation Amendment 17-9