|
---|
Category:Letter
MONTHYEARIR 05000413/20230042024-02-0202 February 2024 Integrated Inspection Report 05000413-2023004 and 05000414-2023004 ML23304A1422024-02-0101 February 2024 Issuance of Environmental Scoping Summary Report Associated with the U.S. Nuclear Regulatory Commission Staffs Review of the Oconee Nuclear Station, Units 1, 2, & 3, Subsequent License Renewal Application IR 05000369/20230042024-01-31031 January 2024 Integrated Inspection Report 05000369/2023004 and 05000370/2023004 ML24005A2512024-01-26026 January 2024 Exemption from Select Requirements of 10 CFR Part 73 - Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting ML24019A1392024-01-25025 January 2024 TSTF 505 and 50.69 Audit Summary ML24019A2002024-01-24024 January 2024 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML24005A2492024-01-24024 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting) IR 05000269/20243012024-01-11011 January 2024 Notification of Licensed Operator Initial Examination 05000269/2024301, 05000270/2024301, and 05000287/2024301 ML23331A7982023-12-14014 December 2023 Review of the Fall 2022 Steam Generator Tube Inspection Report (01R32) IR 05000369/20234022023-12-14014 December 2023 Material Control and Accounting Program Inspection Report 05000369/2023402 and 05000370/2023402 ML23262A9672023-12-13013 December 2023 Alternative to Use RR-22-0174, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems Section XI, Division 1 ML23317A2272023-11-17017 November 2023 William B. McGuire Nuclear Station, Units 1 and 2 - Transmittal of Dam Inspection Report - Non-Proprietary ML23317A3462023-11-14014 November 2023 Duke Fleet - Correction Letter to License Amendment Nos. 312 & 340 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000269/20230032023-11-14014 November 2023 Integrated Inspection Report 05000269/2023003, 05000270/2023003, and 05000287/2023003; and IR 07200040/2023001; and Exercise of Enforcement Discretion IR 05000369/20230032023-10-24024 October 2023 Integrated Inspection Report 05000369/2023003 and 05000370/2023003; and Inspection Report 07200038/2023001 IR 05000369/20240102023-10-13013 October 2023 Notification of McGuire Nuclear Station Comprehensive Engineering Team Inspection U.S. Nuclear Regulatory Commission Inspection Report 05000369, 370/2024010 IR 05000369/20230102023-10-13013 October 2023 Age Related Degradation Inspection Report 05000369/2023010 and 05000370/2023010 IR 05000413/20230102023-10-11011 October 2023 NRC Inspection Report 05000413/2023010 and 05000414/2023010 ML23219A1402023-10-10010 October 2023 Audit Report Proposed Alternative to Use ASME Code Case N-752, Risk Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems XI, Division 1 ML23269A1102023-10-0606 October 2023 Letter to Steven Snider-Revised Schedule for the Environmental Review of the Oconee Nuclear Station, Unit 1, 2, and 3, Subsequent License Renewal Application ML23256A0882023-09-25025 September 2023 Issuance of Alternative to Steam Generator Welds IR 05000369/20233012023-09-20020 September 2023 William B. McGuire Nuclear Station - NRC Examination Report 05000369/2023301 and 05000370/2023301 ML23230A0652023-08-31031 August 2023 William B. McGuire Nuclear Station, Units 1 and 2 - Relief Request Use of Later Edition of ASME Code ML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000269/20230052023-08-25025 August 2023 Updated Inspection Plan for Oconee Nuclear Station Units 1, 2 and 3 (Report 05000269/2023005, 05000270/2023005, and 05000287/2023005) IR 05000269/20230112023-08-25025 August 2023 Comprehensive Engineering Team Inspection Report 05000269/2023011 and 05000270/2023011 and 05000287/2023011 IR 05000413/20230052023-08-25025 August 2023 Updated Inspection Plan for Catawba Nuclear Station Units 1 and 2 (Report 05000413/2023005 and 05000414/2023005) IR 05000369/20230052023-08-25025 August 2023 Updated Inspection Plan for McGuire Nuclear Station Units 1 and 2 (Report 05000369/2023005 and 05000370/2023005) ML23233A1692023-08-17017 August 2023 EN 56683 - Curtiss Wright, Interim Notification Report for PotentialPurt2l IR 05000369/20230022023-07-28028 July 2023 Integrated Inspection Report 05000369/2023002 and 05000370/2023002 IR 05000269/20230022023-07-28028 July 2023 Integrated Inspection Report 05000269/2023002, 05000270/2023002 and 05000287/2023002 ML23208A0972023-07-27027 July 2023 Subsequent License Renewal List of Threatened and Endangered Species That May Occur in Your Proposed Project Location or May Be Affected IR 05000413/20230022023-07-25025 July 2023 Integrated Inspection Report 05000413/2023002 and 05000414/2023002 IR 05000369/20234202023-07-24024 July 2023 Security Baseline Inspection Report 050003692023420 and 050003702023420 ML23206A0092023-07-24024 July 2023 William B. McGuire Nuclear Station Operator Licensing Written Examination Approval 05000369/2023301 and 05000370/2023301 IR 05000269/20230102023-07-19019 July 2023 Biennial Problem Identification and Resolution Inspection Report 05000269/2023010 and 05000270/2023010 and 05000287/2023010 and Notice of Violation ML23207A0762023-07-14014 July 2023 EN 56557 - Update to Part 21 Report Re Potential Defect with Trane External Auto/Stop Emergency Stop Relay Card Pn: XI2650728-06 ML23178A0682023-07-0303 July 2023 Audit Plan Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 & 3 Systems Section XI, Division 1 ML23159A2712023-06-20020 June 2023 William B. McGuire Nuclear Station, Unit 1 - Relief Request Impractical Reactor System Welds ML23237A2672023-06-13013 June 2023 June 13, 2002 - Meeting Announcement - McGuire and Catawba Nuclear Stations 50-369, 50-370 and 50-413, 50-414 ML23159A0052023-06-0505 June 2023 56557-EN 56557 - Paragon - Redlined ML23132A2392023-06-0101 June 2023 Summary of the April 2023 Remote Environmental Audit Related to the Review of the Subsequent License Renewal Application ML23144A0192023-05-25025 May 2023 Review of the Spring 2022 Steam Generator Tube Inspection Report (O3R31) IR 05000269/20230012023-05-12012 May 2023 Integrated Inspection Report 05000269/2023001 and 05000270/2023001 and 05000287/2023001 IR 05000413/20230012023-05-0505 May 2023 Integrated Inspection Report 05000413/2023001 and 05000414/2023001 ML23121A0552023-05-0303 May 2023 Acknowledgement of Withdrawal Request to Revise TS 5.5.2 Containment Leakage Rate Testing Program ML23118A0762023-05-0101 May 2023 Approval for Use of Specific Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML23115A2122023-05-0101 May 2023 Review of the Spring 2022 Steam Generator Tube Inspection Report IR 05000369/20230012023-05-0101 May 2023 Integrated Inspection Report 05000369/2023001 and 05000370/2023001 IR 05000413/20230112023-04-25025 April 2023 Focused Engineering Inspection Report 05000413/2023011 and 05000414/2023011 2024-02-02
[Table view] Category:Report
MONTHYEARML23270B8362023-09-26026 September 2023 Code Case N-752 Audit September 26, 2023, E-mail Providing Additional Information Regarding the Use of Owner'S Requirements and Engineering Judgment in Lieu of Code and Standards ML22269A3882022-09-0707 September 2022 02-Gamma Spectroscopy of Concrete Pucks RA-22-0180, Supplement to Proposed Alternative to Use Reactor Vessel Head Penetration Embedded Flaw Repair for Life of Plant2022-07-0707 July 2022 Supplement to Proposed Alternative to Use Reactor Vessel Head Penetration Embedded Flaw Repair for Life of Plant RA-22-0115, Request for Acceptance of Proposed Method to Manage Aging Due to Environmentally Assisted Fatigue (EAF) for the Safety Injection Nozzle2022-04-21021 April 2022 Request for Acceptance of Proposed Method to Manage Aging Due to Environmentally Assisted Fatigue (EAF) for the Safety Injection Nozzle RA-21-0144, Proposed Alternative to Use Reactor Vessel Head Penetration Embedded Flaw Repair for Life of Plant2022-01-20020 January 2022 Proposed Alternative to Use Reactor Vessel Head Penetration Embedded Flaw Repair for Life of Plant RA-19-0245, of DPC-NE-1007-P, Conditional Exemption of the EOC Mtc Measurement Methodology2021-10-25025 October 2021 of DPC-NE-1007-P, Conditional Exemption of the EOC Mtc Measurement Methodology RA-21-0145, Revision to Proposed Alternative to Use Reactor Vessel Head Penetration Embedded Flaw Repair Method2021-04-24024 April 2021 Revision to Proposed Alternative to Use Reactor Vessel Head Penetration Embedded Flaw Repair Method RA-21-0133, Proposed Alternative to Use Reactor Vessel Head Penetration Embedded Flaw Repair Method2021-04-23023 April 2021 Proposed Alternative to Use Reactor Vessel Head Penetration Embedded Flaw Repair Method RA-20-0363, Post Accident Monitoring Report 369-2020-012020-12-0101 December 2020 Post Accident Monitoring Report 369-2020-01 RA-20-0280, Submittal of IWB-3640 Analytical Evaluation Performed to Accept an ASME Section XI Code Rejected Sub-Surface Flaw2020-09-14014 September 2020 Submittal of IWB-3640 Analytical Evaluation Performed to Accept an ASME Section XI Code Rejected Sub-Surface Flaw ML20150A3322020-04-23023 April 2020 Revision of Slc'S 16-11-2, 16-11-7 and Loes ML19242C7282019-08-28028 August 2019 Attachments 5 - 12: Thermal-Hydraulic Models for High Energy Line Break Transient Analysis, Duke Energy/Framatome Affidavits, Regulatory Requirements, Definitions, Time Critical Operator Actions and Feasibility Assessment for New Proposed T RA-19-0223, Annual Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models Pursuant to 10CFR 50.462019-05-30030 May 2019 Annual Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models Pursuant to 10CFR 50.46 ML19058A4162019-03-0808 March 2019 Staff Evaluation Related to Reactor Vessel Internals Inspection Plan Based on MRP-227-A ML18135A0722018-04-30030 April 2018 ANP-3658, Revision 0, Evaluation of the McGuire Units 1 and 2 Upflow Modification for 60 Years. MNS-17-050, Review Request for the Aging Management Program and Inspection Plan for the Reactor Vessel Internals to Implement MRP-227-A2017-12-13013 December 2017 Review Request for the Aging Management Program and Inspection Plan for the Reactor Vessel Internals to Implement MRP-227-A CNS-17-043, Report 16C4437-RPT-002, Revision 0, 50.54(f) NTTF 2.1 Seismic High Frequency Confirmation for Catawba Nuclear Station.2017-07-0707 July 2017 Report 16C4437-RPT-002, Revision 0, 50.54(f) NTTF 2.1 Seismic High Frequency Confirmation for Catawba Nuclear Station. CNS-17-036, Mid-Cycle Power Uprate Ascension Startup Report2017-06-29029 June 2017 Mid-Cycle Power Uprate Ascension Startup Report ML17171A2772017-06-12012 June 2017 Selected Licensee Commitments List of Revised Effected Sections CNS-17-022, Summary of 10CFR 50.54(q) Evaluation2017-04-25025 April 2017 Summary of 10CFR 50.54(q) Evaluation ML17031A4312017-01-26026 January 2017 Notification of Compliance with Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design Basis External Events and FLEX Final Integrated Plan ML16363A3542016-12-0909 December 2016 54003-CALC-01, Evaluation of Risk Significance of Permanent ILRT Extension. ML16293A6662016-10-31031 October 2016 Staff Assessment of Response to 10 CFR 50.54(f) Information Request - Flood Causing Mechanism Reevaluation (CAC Nos. MF3623 and MF3624) ML16294A2532016-10-12012 October 2016 Issue MNS Technical Specification 5.6 Rev. 2 Amend. 288/267 ML16237A3542016-08-31031 August 2016 Staff Review of Spent Fuel Pool Evaluation Associated with Reevaluated Seismic Hazard Implementing Near-Term Task Force Recommendation 2.1 ML16230A2822016-08-17017 August 2016 Duke Power Company Oconee Nuclear Station Unit 2 Integrated Leak Rate Test of the Reactor Containment Building ML16152A0522016-05-31031 May 2016 ANP-3477NP, Rev. O, MRP-227-A Applicant/Licensee Action Item 6 Analysis ML15253A4102016-03-11011 March 2016 Enclosure 2 Screening Analysis Report ONS-2016-017, Request for Alternative to Codes and Standards Requirements Pursuant to 10 CFR 50.55a(z) to Satisfy 10 CFR 50.55a(h)(2)2016-02-15015 February 2016 Request for Alternative to Codes and Standards Requirements Pursuant to 10 CFR 50.55a(z) to Satisfy 10 CFR 50.55a(h)(2) MNS-16-008, Expedited Seismic Evaluation Process (ESEP) Closeout, Response to NRC Request for Information, Per 10 CFR 50.54(f) Regarding Recommendations 2.1 of the Near-Term Task Force Review of Insights from the Fukushima..2016-02-0404 February 2016 Expedited Seismic Evaluation Process (ESEP) Closeout, Response to NRC Request for Information, Per 10 CFR 50.54(f) Regarding Recommendations 2.1 of the Near-Term Task Force Review of Insights from the Fukushima.. ML16034A3252015-12-31031 December 2015 Revision 0 to Summary of Methodology Used for Seismic Capacity Evaluation of GMRS Mitigation Components CNS-15-101, License Amendment Request (LAR) to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants2015-12-11011 December 2015 License Amendment Request (LAR) to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants ML15313A1642015-10-0808 October 2015 Submittal of 10 CFR 71.95 Report on the 8-120B Cask MNS-15-072, Selected Licensee Commitment Special Report 2015-01, Nuclear Condition Report No. 1943414, Standby Shutdown System Was Non-functional for a Period Greater than 7 Days2015-09-10010 September 2015 Selected Licensee Commitment Special Report 2015-01, Nuclear Condition Report No. 1943414, Standby Shutdown System Was Non-functional for a Period Greater than 7 Days ML15238A7392015-08-24024 August 2015 Submittal of 10 CFR 71.95 Report on the 8-120B Cask ML15246A1452015-08-11011 August 2015 Submittal of 10 CFR 71.95 Report on the 8-120B Cask ML15218A2972015-08-0606 August 2015 Historic Temperature Data Including Record Highs for the Seneca ML15219A5662015-07-29029 July 2015 MNS-TS-5,6 - Distribution to Manual Holders - Amendment 278/258 ML15201A0082015-07-22022 July 2015 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f), Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Review ML15182A0672015-07-20020 July 2015 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(F), Seismic Hazard Reevaluations for Recommendation 2.1 of the Near Term Task Force Review of Insights From.. ML15161A4202015-06-15015 June 2015 Review of the Spring 2014 Steam Generator Tube Inservice Inspection Report During Refueling Outage 27 ONS-2015-065, TIA 2014-04, Request for Technical Assistance Regarding the Adequacy of the Station Design and Licensing Bases for the Degraded Voltage Relay2015-05-22022 May 2015 TIA 2014-04, Request for Technical Assistance Regarding the Adequacy of the Station Design and Licensing Bases for the Degraded Voltage Relay CNS-15-049, Submittal of 2013/2014 10 CFR 50.59 Summary Report of Changes, Tests, Experiments, and Evaluations2015-05-11011 May 2015 Submittal of 2013/2014 10 CFR 50.59 Summary Report of Changes, Tests, Experiments, and Evaluations ML15096A5132015-04-27027 April 2015 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f), Seismic Hazard Revaluations Relating to Recommendation 2.1 of the NTTF Review ML15093A4212015-03-31031 March 2015 Submittal of CNEI-0400-281, Revision 0, Core Operating Limits Reports for Cycle 21 Reload Core, Calculation CNC-1553.05-00-0621 ONS-2015-058, Engineering Report 555, Oconee, Units 1, 2, and 3 - Ul 1569 Impact and Crush Tests on Keowee Underground Trench Power Cables for Duke Energy Carolinas, Llc.2015-03-27027 March 2015 Engineering Report 555, Oconee, Units 1, 2, and 3 - Ul 1569 Impact and Crush Tests on Keowee Underground Trench Power Cables for Duke Energy Carolinas, Llc. CNS-15-031, Commitment Change Evaluation Report for 20142015-03-24024 March 2015 Commitment Change Evaluation Report for 2014 ML16272A2182015-03-0606 March 2015 Revision 1 to Flood Hazard Reevaluation Report on Oconee Nuclear Station, Appendices, Dated March 6, 2015 (Redacted) ML16272A2172015-03-0606 March 2015 Revision 1 to Flood Hazard Reevaluation Report on Oconee Nuclear Station, Pp. 1-70, Dated March 6, 2015 (Redacted) ML15141A0532015-03-0303 March 2015 Enclosure 5, Revision 0 to EP-EALCALC-MNS-1401, MNS Radiological Effluent EAL Values. 2023-09-26
[Table view] Category:Miscellaneous
MONTHYEARML23270B8362023-09-26026 September 2023 Code Case N-752 Audit September 26, 2023, E-mail Providing Additional Information Regarding the Use of Owner'S Requirements and Engineering Judgment in Lieu of Code and Standards RA-22-0115, Request for Acceptance of Proposed Method to Manage Aging Due to Environmentally Assisted Fatigue (EAF) for the Safety Injection Nozzle2022-04-21021 April 2022 Request for Acceptance of Proposed Method to Manage Aging Due to Environmentally Assisted Fatigue (EAF) for the Safety Injection Nozzle ML19242C7282019-08-28028 August 2019 Attachments 5 - 12: Thermal-Hydraulic Models for High Energy Line Break Transient Analysis, Duke Energy/Framatome Affidavits, Regulatory Requirements, Definitions, Time Critical Operator Actions and Feasibility Assessment for New Proposed T RA-19-0223, Annual Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models Pursuant to 10CFR 50.462019-05-30030 May 2019 Annual Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models Pursuant to 10CFR 50.46 ML19058A4162019-03-0808 March 2019 Staff Evaluation Related to Reactor Vessel Internals Inspection Plan Based on MRP-227-A MNS-17-050, Review Request for the Aging Management Program and Inspection Plan for the Reactor Vessel Internals to Implement MRP-227-A2017-12-13013 December 2017 Review Request for the Aging Management Program and Inspection Plan for the Reactor Vessel Internals to Implement MRP-227-A CNS-17-043, Report 16C4437-RPT-002, Revision 0, 50.54(f) NTTF 2.1 Seismic High Frequency Confirmation for Catawba Nuclear Station.2017-07-0707 July 2017 Report 16C4437-RPT-002, Revision 0, 50.54(f) NTTF 2.1 Seismic High Frequency Confirmation for Catawba Nuclear Station. ML17171A2772017-06-12012 June 2017 Selected Licensee Commitments List of Revised Effected Sections CNS-17-022, Summary of 10CFR 50.54(q) Evaluation2017-04-25025 April 2017 Summary of 10CFR 50.54(q) Evaluation ML17031A4312017-01-26026 January 2017 Notification of Compliance with Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design Basis External Events and FLEX Final Integrated Plan ML16293A6662016-10-31031 October 2016 Staff Assessment of Response to 10 CFR 50.54(f) Information Request - Flood Causing Mechanism Reevaluation (CAC Nos. MF3623 and MF3624) ML16294A2532016-10-12012 October 2016 Issue MNS Technical Specification 5.6 Rev. 2 Amend. 288/267 ML16237A3542016-08-31031 August 2016 Staff Review of Spent Fuel Pool Evaluation Associated with Reevaluated Seismic Hazard Implementing Near-Term Task Force Recommendation 2.1 ML16152A0522016-05-31031 May 2016 ANP-3477NP, Rev. O, MRP-227-A Applicant/Licensee Action Item 6 Analysis ML15253A4102016-03-11011 March 2016 Enclosure 2 Screening Analysis Report ONS-2016-017, Request for Alternative to Codes and Standards Requirements Pursuant to 10 CFR 50.55a(z) to Satisfy 10 CFR 50.55a(h)(2)2016-02-15015 February 2016 Request for Alternative to Codes and Standards Requirements Pursuant to 10 CFR 50.55a(z) to Satisfy 10 CFR 50.55a(h)(2) CNS-15-101, License Amendment Request (LAR) to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants2015-12-11011 December 2015 License Amendment Request (LAR) to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants ML15313A1642015-10-0808 October 2015 Submittal of 10 CFR 71.95 Report on the 8-120B Cask MNS-15-072, Selected Licensee Commitment Special Report 2015-01, Nuclear Condition Report No. 1943414, Standby Shutdown System Was Non-functional for a Period Greater than 7 Days2015-09-10010 September 2015 Selected Licensee Commitment Special Report 2015-01, Nuclear Condition Report No. 1943414, Standby Shutdown System Was Non-functional for a Period Greater than 7 Days ML15238A7392015-08-24024 August 2015 Submittal of 10 CFR 71.95 Report on the 8-120B Cask ML15246A1452015-08-11011 August 2015 Submittal of 10 CFR 71.95 Report on the 8-120B Cask ML15218A2972015-08-0606 August 2015 Historic Temperature Data Including Record Highs for the Seneca ML15201A0082015-07-22022 July 2015 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f), Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Review ML15182A0672015-07-20020 July 2015 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(F), Seismic Hazard Reevaluations for Recommendation 2.1 of the Near Term Task Force Review of Insights From.. ML15161A4202015-06-15015 June 2015 Review of the Spring 2014 Steam Generator Tube Inservice Inspection Report During Refueling Outage 27 CNS-15-049, Submittal of 2013/2014 10 CFR 50.59 Summary Report of Changes, Tests, Experiments, and Evaluations2015-05-11011 May 2015 Submittal of 2013/2014 10 CFR 50.59 Summary Report of Changes, Tests, Experiments, and Evaluations ML15096A5132015-04-27027 April 2015 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f), Seismic Hazard Revaluations Relating to Recommendation 2.1 of the NTTF Review ML15093A4212015-03-31031 March 2015 Submittal of CNEI-0400-281, Revision 0, Core Operating Limits Reports for Cycle 21 Reload Core, Calculation CNC-1553.05-00-0621 ONS-2015-058, Engineering Report 555, Oconee, Units 1, 2, and 3 - Ul 1569 Impact and Crush Tests on Keowee Underground Trench Power Cables for Duke Energy Carolinas, Llc.2015-03-27027 March 2015 Engineering Report 555, Oconee, Units 1, 2, and 3 - Ul 1569 Impact and Crush Tests on Keowee Underground Trench Power Cables for Duke Energy Carolinas, Llc. CNS-15-031, Commitment Change Evaluation Report for 20142015-03-24024 March 2015 Commitment Change Evaluation Report for 2014 ML15141A0532015-03-0303 March 2015 Enclosure 5, Revision 0 to EP-EALCALC-MNS-1401, MNS Radiological Effluent EAL Values. ML15072A2172015-02-25025 February 2015 Form OAR-1 Owners Activity Report (CC N-532-4) for Oconee Unit 1, Refueling Outage EOC 28 MNS-15-004, Annual Commitment Change Report2015-01-29029 January 2015 Annual Commitment Change Report ONS-2014-161, Submittal of the Expedited Seismic Evaluation Process Report (CEUS Sites)2014-12-19019 December 2014 Submittal of the Expedited Seismic Evaluation Process Report (CEUS Sites) ML14218A8072014-08-27027 August 2014 NRC Staff Review of the Documentation Provided by Duke Energy for the Oconee Nuclear Station Concerning Resolution of GL 2004-02 Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Wat ONS-2014-074, Special Report Per Selected Licensee Commitment 16.9.9 Auxiliary Service Water (Asw) System and Main Steam Atmospheric Dump Valves and Oconee Transition from the Station Asw System to the Protected Service Water System2014-08-15015 August 2014 Special Report Per Selected Licensee Commitment 16.9.9 Auxiliary Service Water (Asw) System and Main Steam Atmospheric Dump Valves and Oconee Transition from the Station Asw System to the Protected Service Water System CNS-14-131, WCAP-17669-NP, Revision 0, Catawba Unit 1 Measurement Uncertainty Recapture (Mur) Power Uprate: Reactor Vessel Integrity and Neutron Fluence Evaluations2014-06-30030 June 2014 WCAP-17669-NP, Revision 0, Catawba Unit 1 Measurement Uncertainty Recapture (Mur) Power Uprate: Reactor Vessel Integrity and Neutron Fluence Evaluations ML14156A2872014-06-10010 June 2014 Staff Assessment of the Flooding Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-ichi Nuclear Power Plant Accident ML14108A2012014-05-16016 May 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident ML14114A3052014-05-0808 May 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-ichi Nuclear Power Plant Accident ML14085A0652014-04-24024 April 2014 NRC Staff Review of the Documentation Provided by Duke Energy Carolinas, LLC, for McGuire Concerning Resolution of Generic LTR 2004-02 Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressuriz ML14076A0002014-04-0202 April 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima DAI-ICHI Nuclear Power Plant Accident CNS-14-045, Commitment Change Evaluation Report for 20132014-03-31031 March 2014 Commitment Change Evaluation Report for 2013 ONS-2014-040, 2013 Annual Commitment Change Report2014-03-31031 March 2014 2013 Annual Commitment Change Report MNS-14-029, Seismic Hazard and Screening Report (CEUS Sites), Response to NRC 10 CFR 50.54(f) Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3 and 9.3 of The.2014-03-20020 March 2014 Seismic Hazard and Screening Report (CEUS Sites), Response to NRC 10 CFR 50.54(f) Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3 and 9.3 of The. MNS-14-030, Annual Commitment Change Report2014-03-19019 March 2014 Annual Commitment Change Report ONS-2014-002, Special Report Per Technical Specification 5.6.6, Problem Investigation Process No. O-13-144472014-01-16016 January 2014 Special Report Per Technical Specification 5.6.6, Problem Investigation Process No. O-13-14447 ML13338A5772013-09-30030 September 2013 Oig Semiannual Report to Congress - Fall 2013 ML13196A2482013-07-11011 July 2013 Duke Energy Carolinas, LLC (Duke Energy): Report Pursuant to 10 CFR 50.46, Changes to or Errors in an Evaluation Model ML13190A0152013-07-0101 July 2013 Aging Management Reviews for Newly Identified Systems, Structures and Components as of December 31, 2012 2023-09-26
[Table view] |
Text
Duke Power P Duke 526 South Church St. EC07H wPower Charlotte, NC 28202 A Duke Energy Company P. O. Box 1006 EC07H Charlotte, NC 28201-1006 (704) 382-2200 OFFICE M. S. Tuckman (704) 382-4360 FAX Executive Vice President Nuclear Generation February 28, 2002 U. S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555
Subject:
Duke Energy Corporation Fitness-For-Duty Program Performance Data Reports Oconee Nuclear Station, Docket Nos. 50-269, -270, -287 McGuire Nuclear Station, Docket Nos. 50-369, -370 Catawba Nuclear Station, Docket Nos. 50-413, -414 Pursuant to 10 CFR 26.71(d), enclosed are the subject reports for Duke Energy Corporation's Oconee, McGuire and Catawba Nuclear Stations and the General Office. The reporting period covered by this transmittal is July 1, 2001 through December 31, 2001.
Results reflected in this report are typical of other periods.
Questions regarding these reports should be directed to Peter R.
Fowler at 704-382-6188 or Mike Cash at 704-382-5826.
Sincerely, M. S. Tuckman Attachment Y
U. S. Nuclear Regulatory Commission February 28, 2002 Page Two CC: w/attachment L. A. Reyes Regional Administrator, Region II U. S. Nuclear Regulatory Commission Atlanta Federal Center, Suite 23T85 61 Forsyth Street, S.W.
Atlanta. GA 30303-3415 C. P. Patel, NRC Senior Project Manager (CNS)
U. S. Nuclear Regulatory Commission Mail Stop 0-14 H25 Washington, D. C. 20555-0001 R. E. Martin, NRC Project Manager (MNS)
U. S. Nuclear Regulatory Commission Mail Stop 0-8 H12 Washington, D. C. 20555-0001 L. N. Olshan, NRC Project Manager (ONS)
U. S. Nuclear Regulatory Commission Mail Stop 0-8 H12 Washington, D. C. 20555-0001
Fitness for Duty Program Performance Data Personnel Subject to 10 CFR 26 12/31/01 DUKE POWER COMPANY Company 6 Month Ending Catawba Nuclear Station Location Anita Barnette (704) 382-4904 Contact Name Phone (Include area code)
Cutoffs: Screen/Confirmation (ng/ml) [ Appendix A to 10 CFR 26 Marijuana 50 ng/ml / 15ng/ml Amphetamines 1000 ng/ml / 500 ng/ml _________________________ /
Cocaine 300 ng/ml /150 ng/ml Phencyclidine 25 ng/ml / 25 ng/ml _________________________ /
Opiates 300 ng/ml / 300 ng/ml Alcohol (%BAC) .04 /
Short-Term Long-Term Short-Term Testing Results Licensee Employees Contractor Personnel Contractor Personnel Average Number with 1360 221 Unescorted Access Categories # Tested # Positive * # Tested I# Positive * # Tested # Positive
- Pre-Access 130 1 544 10 For Cause - Post 0 0 0 0 Accident For Cause - Observed 2 0 1 0 Behavior Random 393 1 111 1 Follow-up 23 0 5 1 Other 2 0 0 0 Total 550 2 661 12 Rev. 1/92
Breakdown of Confirmed Positive Tests for Specific Substances - Catawba Nuclear Station (for 6 Month Ending 12/31/01)
Licensee Employees Long-Term Contractors Short-Term Contractors
Attachment A Fitness for Duty Program Performance Data Personnel Subject to 10CFR 26 (for Catawba Nuclear Station) for 6 Month Ending 12/31/01 Summary of Management Actions:
(Include initiatives taken, lessons learned, effectiveness evaluation, etc. as appropriate.)
- Duke Power has more restrictive cut-off levels for Alcohol and Marijuana. In the past, Duke Power has shown this detail on the Performance Data Report's first sheet. Beginning with the last semi-annual report (period ending 06/30/01), Duke Power will provide a more detailed report that will indicate positive test results confirmed at the NRC cut-off level and Duke Power's cut-off level. This detailed report for the period ending 12/31/01 is attached (see Attachment B).
Summary Listing of Events Reported Under 10 CFR 26.73:
Date of Position of How Discovered Substance Management Actions Taken Event Individual Detected Involved None during this reporting period
Attachment B Fitness for Duty Program Performance Data Personnel Subject to 10CFR 26 (for Catawba Nuclear Station) 6 Month Ending - 12/31/01 POSITIVE Cut-Off Level Detail Report (NRC / Duke Level)
Long-Term Short-Term Testing Results Licensee Employees Contractor Personnel Contractor Personnel Average Number with 1360 221 Unescorted Access Categories # Tested # Positive * # Tested # Positive * # Tested # Positive
- Pre-Access NRC Duke NRC Duke 130 0 544 7 3 For Cause - Post Accident 0 0 0 0 0 0 For Cause - Observed Behavior 2 0 0 1 0 0 Random 393 0 I111 1 0 Follow-up 23 0 0 5 1 0 Other 2 0 I 0 - --- - -- -- 0 0 0 Total 550 0 I2 661 9 3 SUBSTANCE Cut-Off Level Detail Report (NRC / Duke Level)
Marijuana Cocaine Opiates Amphe- Phency- Alcohol Refusal 1 2 3 4 5 TOTAL
- to Test NRC Duke NRC Duke Licensee Employees 0 2 0 0 0 0 0 0 0 2 Long-Term Contractors Short-Term Contractors 2 3 3 0 1 0 2 0 1 12 Total 2 5 3 0 1 0 2 0 1 14
Fitness for Duty Program Performance Data Personnel Subject to 10 CFR 26 12/31/01 DUKE POWER COMPANY Company 6 Month Ending McGuire Nuclear Station Location Anita Barnette (704) 382-4904 Contact Name Phone (Include area code)
Cutoffs: Screen/Confirmation (ng/ml) El Appendix A to 10 CFR 26 Marijuana 50 ng/ml / 15 ng/ml Amphetamines 1000 ng/ml / 500 ng/ml ________________________ /
Cocaine 300 ng/ml /150 ng/ml Phencyclidine 25 ng/ml / 25 ng/ml ___________________________ /
Opiates 300 ng/ml / 300 ng/ml Alcohol (%BAC) .04 _______________________ I Long-Term Short-Term Testing Results Licensee Employees Contractor Personnel Contractor Personnel Average Number with 1378 199 Unescorted Access Categories # Tested # Positive * # Tested I# Positive * # Tested # Positive
- Pre-Access 48 0 125 4 For Cause - Post 0 0 1 0 Accident For Cause - Observed 1 0 1 1 Behavior Random 389 0 96 2 Follow-up 17 1 1 1 Other 2 0 0 0 Total 457 1 224 8 Rev. 1/92
Breakdown of Confirmed Positive Tests for Specific Substances - McGuire Nuclear Station (for 6 Month Ending 12/31/01)
A
Attachment A Fitness for Duty Program Performance Data Personnel Subject to 10CFR 26 (for McGuire Nuclear Station) for 6 Month Ending 12/31/01 Summary of Management Actions:
(Include initiatives taken, lessons learned, effectiveness evaluation, etc. as appropriate.)
- Duke Power has more restrictive cut-off levels for Alcohol and Marijuana. In the past, Duke Power has shown this detail on the Performance Data Report's first sheet. Beginning with the last semi-annual report (period ending 06/30/01), Duke Power will provide a more detailed report that will indicate positive test results confirmed at the NRC cut-off level and Duke Power's cut-off level. This detailed report for the period ending 12/31/01 is attached (see Attachment B).
Summary Listing of Events Reported Under 10 CFR 26.73:
Date of Position of How Discovered Substance Management Actions Taken Event Individual Detected Involved None during this reporting period
Attachment B Fitness for Duty Program Performance Data Personnel Subject to 10CFR 26 (for McGuire Nuclear Station) 6 Month Ending 12/31/01 POSITIVE Cut-Off Level Detail Report (NRC / Duke Level)
Long-Term Short-Term Testing Results Licensee Employees Contractor Personnel Contractor Personnel Average Number with 1378 199 Unescorted Access Categories # Tested # Positive * # Tested # Positive * # Tested # Positive
- Pre-Access NRC Duke NRC Duke 48 0 0 125 3 1 For Cause - Post Accident 0 0 0 1 0 0 For Cause - Observed Behavior 1 0 0 1 1 0 Random 389 0 096 2 0 Follow-up 17 0 1 1 1 0 Other 2 0 0 0 0 0 Total 224 7 1 457 0 1 SUBSTANCE Cut-Off Level Detail Report (NRC / Duke Level)
Marijuana Cocaine Opiates Amphe- Phency- Alcohol Refusal 1 2 3 4 5 TOTAL
- to Test NRC Duke NRC Duke Licensee Employees 0 1 0 0 0 0 0 0 0 1 Long-Term Contratr Short-Term Contractors 4 1 0 0 0 0 1 0 2 8 Total 4 2 0 0 0 0 1 0 2 9
Fitness for Duty Program Performance Data Personnel Subject to 10 CFR 26 12/31/01 DUKE POWER COMPANY Company 6 Month Ending Oconee Nuclear Station Location Anita Barnette (704) 382-4904 Contact Name Phone (Include area code)
Cutoffs: Screen/Confirmation (ng/ml) El Appendix A to 10 CFR 26 Marijuana 50 ng/mI / 15ng/ml Amphetamines 1000 ng/ml / 500 ng/ml /
Phencyclidine 25 ng/ml / 25 ng/ml /
Cocaine 300 ng/ml /150 ng/ml Alcohol (%BAC) .04 /
Opiates 300 ng/ml / 300 ng/ml Long-Term Short-Term Testing Results Licensee Employees Contractor Personnel Contractor Personnel Average Number with 1495 560 Unescorted Access Categories # Tested # Positive * # Tested I # Positive * # Tested # Positive
- Pre-Access 87 0 228 7 For Cause - Post 0 0 0 0 Accident For Cause - Observed 1 0 0 0 Behavior Random 391 0 201 2 Follow-up 16 0 1 0 Other 1 0 1 0 Total 496 0 431 9 Rev. 1/92
Breakdown of Confirmed Positive Tests for Specific Substances - Oconee Nuclear Station (for 6 Month Ending 12/31/01)
- Two individuals positive for two substances each.
Attachment A Fitness for Duty Program Performance Data Personnel Subject to 10CFR 26 (for Oconee Nuclear Station) for 6 Month Ending 12/31/01 Summary of Management Actions:
(Include initiatives taken, lessons learned, effectiveness evaluation, etc. as appropriate.)
- Duke Power has more restrictive cut-off levels for Alcohol and Marijuana. In the past, Duke Power has shown this detail on the Performance Data Report's first sheet. Beginning with the last semi-annual report (period ending 06/30/01), Duke Power will provide a more detailed report that will indicate positive test results confirmed at the NRC cut-off level and Duke Power's cut-off level. This detailed report for the period ending 12/31/01 is attached (see Attachment B).
Summary Listing of Events Reported Under 10 CFR 26.73:
Date of Position of How Discovered Substance Management Actions Taken Event Individual Detected Involved None during this reporting period
Attachment B Fitness for Duty Program Performance Data Personnel Subject to 10CFR 26 (for Oconee Nuclear Station) for 6 Month Ending 12/31/01 POSITIVE Cut-Off Level Detail Report (NRC / Duke Level)
Long-Term Short-Term Testing Results Licensee Employees Contractor Personnel Contractor Personnel Average Number with 1495 560 Unescorted Access Categories # Tested # Positive * # Tested # Positive * # Tested # Positive
- Pre-Access NRC Duke NRC Duke 87 0 0 228 6 I 1 For Cause - Post Accident 0 0 0 0 0 0 For Cause - Observed Behavior 1 0 0 0 0 0 Random 391 0 0 201 1 I 1 Follow-up 16 0 0 1 _0 0 Other 1 0 0 -1 0 0 Total 496 0 0 431 7 1 2 SUBSTANCE Cut-Off Level Detail Report (NRC I Duke Level)
Marijuana Cocaine Opiates Amphe- Phency- Alcohol Refusal 1 2 3 4 5 TOTAL
- to Test NRC Duke NRC Duke Licensee Employees 0 0 0 0 0 0 0 0 0 0 Long-Term Contractors Short-Term Contractors 4 1 4 0 0 0 1 1 0 11 Total 4 1 4 0 0 0 1 1 0 11*
- Two individuals positive for two substances each.
Fitness for Duty Program Performance Data Personnel Subject to 10 CFR 26 12/31/01 DUKE POWER COMPANY Company 6 Month Ending General Office Location Anita Barnette (704) 382-4904 Contact Name Phone (Include area code)
Cutoffs: Screen/Confirmation (ng/ml) [ Appendix A to 10 CFR 26 Marijuana 50 ng/ml / 15 ng/ml Amphetamines 1000 ng/ml I 500 ng/ml /
300 ng/ml /150 ng/ml Phencyclidine 25 ng/ml / 25 ng/ml /
Cocaine Opiates 300 ng/ml / 300 ng/ml Alcohol (%BAC) .04 /
Long-Term Short-Term Testing Results Licensee Employees Contractor Personnel Contractor Personnel Average Number with 455 Unescorted Access
- Tested # Positive * # Tested # Positive * # Tested # Positive
- Categories 46 0 4 ** 0 Pre-Access 0 0 0 0 For Cause - Post Accident 0 0 0 For Cause - Observed Behavior 192 0 0 0 Random 3 0 0 0 Follow-up 0 0 0 0 Other 0 4** 0 Total 241 Rev. 1/92
Breakdown of Confirmed Positive Tests for Specific Substances - Duke Power Company General Office (for 6 Month Ending 12/31/01)
Marijuana Cocaine Opiates Amphe- Phency- Alcohol Refusal 1 2 3 5
, tamines clidine
- To Test Licensee Employees 0 0 0 0 0 0oo I I I I Long-Term Contractors Short-Term Contractors 0 0 0 0 0 0 1 Total 0 0 0 0 0 0 0 A
Attachment A Fitness for Duty Program Performance Data Personnel Subject to 10CFR 26 (for Duke Power Company General Office) for 6 Month Ending 12/31/01 Summary of Management Actions:
(Include initiatives taken, lessons learned, effectiveness evaluation, etc. as appropriate.)
this
- Duke Power has more restrictive cut-off levels for Alcohol and Marijuana. In the past, Duke Power has shown (period ending detail on the Performance Data Report's first sheet. Beginning with the last semi-annual report that will indicate positive test results confirmed at the NRC 06/30/01), Duke Power will provide a more detailed report the period ending 12/31/01 is attached (see cut-off level and Duke Power's cut-off level. This detailed report for Attachment B).
Program
- Duke Power Company approved the Pre-Access Testing portion of Westinghouse's Fitness for Duty "Short Term Contractor Personnel" are effective August 3, 1999. The 4 Pre-Access screens reported under being reported with Duke Power Company performance data as a result of accepting Westinghouse's program.
Summary Listing of Events Reported Under 10 CFR 26.73:
MaaeetAtosIae Date of Position of How Discovered Substance Management Actions Taken Individual Detected Event Involved
_____ £ + t None during this reporting perli xli I _____________I I_____________I_____
OG
Attachment B Fitness for Duty Program Performance Data Personnel Subject to 10CFR 26 (for Duke Power Company General Office) for 6 Month Ending 12/31/01 POSITIVE Cut-Off Level Detail Report (NRC / Duke Level)
Long-Term Short-Term Testing Results Licensee Employees Contractor Personnel Contractor Personnel Average Number with 455 Unescorted Access Categories # Tested # Positive * # Tested # Positive * # Tested #Positive
- NRC Duke Pre-Access NRC Duke 4 ** 0 0 46 0 0 For Cause - Post 0 0 0 Accident 0 0 0 For Cause - Observed Behavior 0 0 0 o 0 0 Random 0 0 0 0 0 192 Follow-up 0 0 0 3 0 0 Other 0 0 0 0 0 0 Total 4 ** 0 0
______________ 241 0 0 SUBSTANCE Cut-Off Level Detail Report (NRC / Duke Level)