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Category:Letter
MONTHYEARIR 05000369/20230042024-01-31031 January 2024 Integrated Inspection Report 05000369/2023004 and 05000370/2023004 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 IR 05000369/20234022023-12-14014 December 2023 Material Control and Accounting Program Inspection Report 05000369/2023402 and 05000370/2023402 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 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 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 05000369/20230052023-08-25025 August 2023 Updated Inspection Plan for McGuire Nuclear Station Units 1 and 2 (Report 05000369/2023005 and 05000370/2023005) IR 05000369/20230022023-07-28028 July 2023 Integrated Inspection Report 05000369/2023002 and 05000370/2023002 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 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 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 ML23115A2122023-05-0101 May 2023 Review of the Spring 2022 Steam Generator Tube Inspection Report 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 IR 05000369/20230012023-05-0101 May 2023 Integrated Inspection Report 05000369/2023001 and 05000370/2023001 ML23094A1832023-04-18018 April 2023 Audit Plan TSTF-505, Rev. 2, RITSTF Initiative 4B & 10 CFR 50.69, Risk-Informed Categorization & Treatment of Structures, Systems & Components for Nuclear Power Reactors (EPIDs L-2023-LLA-0021 & L-2023-LLA-0022) ML22332A4932023-03-10010 March 2023 William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility IR 05000369/20220062023-03-0101 March 2023 Annual Assessment Letter for McGuire Nuclear Station Units 1 and 2 (NRC Inspection Report 05000369/2022006 and 05000370 2022006) IR 05000369/20220042023-01-30030 January 2023 Mcguire Nuclear Station - Integrated Inspection Report 05000369/2022004 and 05000370/2022004 IR 05000369/20224202023-01-11011 January 2023 Security Baseline Inspection Report 05000369/2022420 and 05000370/2022420 ML22356A0512022-12-14014 December 2022 Curtiss-Wright Nuclear Division, Letter Regarding Potential Efect in a Configuration of the 11/2 Inch Quick Disconnect Connector Cable Assemblies Supplied to Duke Energy (See Attached Spreadsheet) for a Total of 460 of Connectors Only Suppl ML22347A1512022-12-13013 December 2022 William B. Mcguire Nuclear Station Notification of Licensed Operator Initial Examination 05000369/2023301 and 05000370/2023301 ML22340A6662022-12-0808 December 2022 Summary of November 30, 2022, Public Meeting with Duke Energy Carolinas, LLC for McGuire Nuclear Station, Units 1 & 2 Proposed LAR to Adopt TSTF-505, Rev. 2 and 10 CFR 50.69 Risk-Informed Categorization and Treatment of Structures, Systems ML22290A1012022-11-29029 November 2022 Issuance of Amendment Nos. 326 and 305, Regarding Changes to Technical Specification 3.4.3, Reactor Coolant System Pressure Temperature Limits ML22096A0032022-11-18018 November 2022 McGuire Nuclear Station and Shearon Harris Nuclear Power Plant Authorization of RA-19-0352 Regarding Use of Alternative for RPV Head Closure Stud Examinations ML22256A2532022-11-14014 November 2022 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-541, Rev. 2 IR 05000369/20220032022-10-27027 October 2022 Integrated Inspection Report 05000369/2022003 and 05000370/2022003 IR 05000369/20220112022-09-29029 September 2022 Biennial Problem Identification and Resolution Inspection Report 05000369/2022011 and 05000370/2022011 ML22266A0782022-09-26026 September 2022 William B. Mcguire Nuclear Station, Unit 2 Pressurizer Power Operated Relief Valve Relief Request ML22258A0302022-09-15015 September 2022 Evacuation Time Estimate Reports ML22242A0022022-09-12012 September 2022 Issuance of Amendments to Adopt TSTF 569, Revision 2, Revise Response Time Testing Definition IR 07200038/20220012022-09-12012 September 2022 Operation of an Independent Spent Fuel Storage Installation Report 07200038/2022001 ML22230B6132022-09-0101 September 2022 Review of the Draft Environmental Assessment and Finding of No Significant Impact for Brunswick Steam Electric Plant and McGuire Nuclear Station Independent Spent Fuel Storage Installations Decommissioning Funding Plans IR 05000369/20220052022-08-29029 August 2022 Updated Inspection Plan for McGuire Nuclear Station Units 1 and 2 NRC Inspection Report 05000369/2022005 and 05000370/2022005 IR 05000369/20220022022-07-26026 July 2022 Integrated Inspection Report 05000369/2022002 and 05000370/2022002 ML22215A2502022-07-25025 July 2022 EN 55960 - Update - Curtiss Wright ML22164A0362022-07-19019 July 2022 Mcguire Nuclear Station, Units 1 and 2; Issuance of Amendments to Revise the Conditional Exemption of the End-Of-Cycle Moderator Temperature Coefficient Measurement Methodology (EPID L-2021-LLA-0198) Public ML22175A0162022-06-24024 June 2022 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML22046A0222022-06-14014 June 2022 Issuance of Amendments to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO ML22111A3112022-05-16016 May 2022 Letter Issuing Exemption to McGuire IR 05000369/20224012022-05-12012 May 2022 Cyber Security Inspection Report 05000369/2022401 and 05000370/2022401 2024-01-31
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARRA-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 RA-18-0090, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-02-17017 February 2023 Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors RA-18-0190, License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2023-02-16016 February 2023 License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b RA-22-0091, Application to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2023-02-16016 February 2023 Application to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements RA-22-0118, License Amendment Request to Revise Restrictive Technical Specification Surveillance Requirement Frequencies2023-02-0101 February 2023 License Amendment Request to Revise Restrictive Technical Specification Surveillance Requirement Frequencies RA-21-0302, Application to Revise Technical Specifications to Adopt TSTF-569, Rev. 2, Revise Response Time Testing Definition2022-02-24024 February 2022 Application to Revise Technical Specifications to Adopt TSTF-569, Rev. 2, Revise Response Time Testing Definition RA-20-0107, Duke Energy Progress, LLC, and Duke Energy Carolinas, LLC, Application to Revise Technical Specifications to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2022-01-18018 January 2022 Duke Energy Progress, LLC, and Duke Energy Carolinas, LLC, Application to Revise Technical Specifications to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position RA-21-0320, License Amendment Request (LAR) to Revise the Applicability Term for Pressure and Temperature Limit Curves of Technical Specification 3.4.3, RCS Pressure and Temperature (P/T) Limits2021-12-20020 December 2021 License Amendment Request (LAR) to Revise the Applicability Term for Pressure and Temperature Limit Curves of Technical Specification 3.4.3, RCS Pressure and Temperature (P/T) Limits RA-21-0197, William, Units 1 and 2, License Amendment Request to Relocate the Duke Energy Emergency Operations Facility2021-12-14014 December 2021 William, Units 1 and 2, License Amendment Request to Relocate the Duke Energy Emergency Operations Facility RA-19-0043, Duke Energy - Application to Revise Technical Specifications to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO2021-06-0909 June 2021 Duke Energy - Application to Revise Technical Specifications to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO RA-19-0006, License Amendment Application to Relocate Technical Specification Unit/Facility Staff Qualification ANSI N18.1-1971, ANSI/ANS-3.1-1978 and ANSI/ANS-3.1-1981 Requirements to the Duke Energy Corporation Quality Assurance Program Description2019-07-0808 July 2019 License Amendment Application to Relocate Technical Specification Unit/Facility Staff Qualification ANSI N18.1-1971, ANSI/ANS-3.1-1978 and ANSI/ANS-3.1-1981 Requirements to the Duke Energy Corporation Quality Assurance Program Description RA-18-001, McGuire Nuclear Station, Units 1 and 2 - Supplement to License Amendment Request Proposing Changes to Catawba and McGuire Technical Specification 3.8.1, AC Sources - Operating.2018-07-10010 July 2018 McGuire Nuclear Station, Units 1 and 2 - Supplement to License Amendment Request Proposing Changes to Catawba and McGuire Technical Specification 3.8.1, AC Sources - Operating. RA-18-0015, Supplement to License Amendment Request Proposing Changes to Catawba and McGuire Technical Specification 3.8.1, AC Sources - Operating.2018-07-10010 July 2018 Supplement to License Amendment Request Proposing Changes to Catawba and McGuire Technical Specification 3.8.1, AC Sources - Operating. MNS-18-001, Application to Revise Technical Specifications to Adopt TSTF-234-A Revision 1, Add Action for More than One Dpri Inoperable2018-05-31031 May 2018 Application to Revise Technical Specifications to Adopt TSTF-234-A Revision 1, Add Action for More than One Dpri Inoperable ML18130A8072018-05-10010 May 2018 Duke Energy Progress, LLC and Duke Energy Carolinas, LLC - Submittal of License Amendment Application to Remove Heaters from Ventilation System Technical Specifications RA-18-000, Duke Energy Progress, LLC and Duke Energy Carolinas, LLC - Submittal of License Amendment Application to Remove Heaters from Ventilation System Technical Specifications2018-05-10010 May 2018 Duke Energy Progress, LLC and Duke Energy Carolinas, LLC - Submittal of License Amendment Application to Remove Heaters from Ventilation System Technical Specifications MNS-18-017, Non-Voluntary License Amendment Request (LAR) to Correct Non-Conservative Technical Specification 3.4.11 - PORVs2018-02-26026 February 2018 Non-Voluntary License Amendment Request (LAR) to Correct Non-Conservative Technical Specification 3.4.11 - PORVs MNS-17-026, Submittal of License Amendment Request Proposing to Revise the Bases for Protection from Tornado-Generated Missiles2017-12-0808 December 2017 Submittal of License Amendment Request Proposing to Revise the Bases for Protection from Tornado-Generated Missiles RA-17-0005, Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing2017-11-0707 November 2017 Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing MNS-17-031, License Amendment Request for Temporary Changes to Technical Specifications to Address an 'A' Train Nuclear Service Water System (Nsws) Non-Conforming Condition2017-09-14014 September 2017 License Amendment Request for Temporary Changes to Technical Specifications to Address an 'A' Train Nuclear Service Water System (Nsws) Non-Conforming Condition RA-17-0035, Supplement to License Amendment Request Proposing Changes to Technical Specification 3.5.1, AC Sources - Operating.2017-07-20020 July 2017 Supplement to License Amendment Request Proposing Changes to Technical Specification 3.5.1, AC Sources - Operating. RA-17-0001, Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules2017-07-18018 July 2017 Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules MNS-17-023, Response to Request for Additional Information to License Amendment Request Permanent Extension of Type a and Type C Leak Rate Test Frequencies2017-05-25025 May 2017 Response to Request for Additional Information to License Amendment Request Permanent Extension of Type a and Type C Leak Rate Test Frequencies ML17122A1162017-05-0202 May 2017 Catawba and McGuire - License Amendment Request Proposing Changes to Technical Specification 3.8.1, AC Sources - Operating. RA-17-0003, Application to Revise Technical Specifications to Adopt Multiple Technical Specification Task Force Travelers2017-01-11011 January 2017 Application to Revise Technical Specifications to Adopt Multiple Technical Specification Task Force Travelers MNS-16-092, License Amendment Request to Revise Technical Specifications Section 5.5.2, Containment Leakage Rate Testing Program for Permanent Extension of Type a and Type C Leak Rate Test Frequencies2016-12-19019 December 2016 License Amendment Request to Revise Technical Specifications Section 5.5.2, Containment Leakage Rate Testing Program for Permanent Extension of Type a and Type C Leak Rate Test Frequencies MNS-16-091, License Amendment Request for Technical Specification 3.6.14, Divider Barrier Integrity.2016-12-0808 December 2016 License Amendment Request for Technical Specification 3.6.14, Divider Barrier Integrity. ML16305A1412016-10-20020 October 2016 Document Transmittal Regarding Issue MNS FOL U-2, Rev. 3 RA-16-0019, Duke Energy Progress - Application to Revise Technical Specifications to Adopt TSTF-522, Revision 0, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month Using the Consolidated Line Item Improvement Proces2016-09-27027 September 2016 Duke Energy Progress - Application to Revise Technical Specifications to Adopt TSTF-522, Revision 0, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month Using the Consolidated Line Item Improvement Process MNS-16-046, License Amendment Request for Technical Specification 3.6.14, Divider Barrier Integrity2016-06-30030 June 2016 License Amendment Request for Technical Specification 3.6.14, Divider Barrier Integrity MNS-16-039, Submittal Revising Attachment s of License Amendment Request to Implement a Risk-Informed Performance-Based Fire Protection Program2016-04-26026 April 2016 Submittal Revising Attachment s of License Amendment Request to Implement a Risk-Informed Performance-Based Fire Protection Program MNS-15-068, License Amendment Request to Technical Specification (TS) 3.6.13, Ice Condenser Doors.2016-03-24024 March 2016 License Amendment Request to Technical Specification (TS) 3.6.13, Ice Condenser Doors. MNS-16-015, License Amendment Request (LAR) for One-Time Extension of Appendix J Type a Integrated Leakage Rate Test Interval2016-02-18018 February 2016 License Amendment Request (LAR) for One-Time Extension of Appendix J Type a Integrated Leakage Rate Test Interval MNS-15-099, Submittal Regarding License Amendment Request to Implement a Risk-Informed Performance-Based Fire Protection Program2016-01-14014 January 2016 Submittal Regarding License Amendment Request to Implement a Risk-Informed Performance-Based Fire Protection Program MNS-16-002, Proposed Technical Specifications (TS) Amendment TS 3.7.10, Control Room Area Chilled Water System (Mns), and TS 3.7.11, Control Room Area Chilled Water System (CNS)2016-01-0707 January 2016 Proposed Technical Specifications (TS) Amendment TS 3.7.10, Control Room Area Chilled Water System (Mns), and TS 3.7.11, Control Room Area Chilled Water System (CNS) ML15258A0582015-09-0909 September 2015 Amendment 280 ML15258A0592015-09-0909 September 2015 Renewed Facility Operating License ML15258A0552015-09-0808 September 2015 Renewed Facility Operating License ML15258A0572015-09-0808 September 2015 Mcgurie Nuclear Station - MNS-TS-1.1 Amendment 280/260 Distribution MNS-15-069, Duke Energy Carolinas, LLC (Duke Energy), McGuire Nuclear Station, Unit 1 - License Amendment Request for One-Time Change to Technical Specification 3.5.2, Emergency Core Cooling Systems (ECCS) - Operating.2015-08-28028 August 2015 Duke Energy Carolinas, LLC (Duke Energy), McGuire Nuclear Station, Unit 1 - License Amendment Request for One-Time Change to Technical Specification 3.5.2, Emergency Core Cooling Systems (ECCS) - Operating. RA-15-0020, License Amendment Request and 10 CFR 50.12 Exemption Request for Use of Optimized Zirlo Fuel Rod Cladding2015-08-20020 August 2015 License Amendment Request and 10 CFR 50.12 Exemption Request for Use of Optimized Zirlo Fuel Rod Cladding RA-15-001, Catawba, McGuire, and Oconee - License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 3, Foot2015-07-15015 July 2015 Catawba, McGuire, and Oconee - License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 3, Footn RA-15-0013, License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 3, Footnote 112015-07-15015 July 2015 License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 3, Footnote 11 MNS-15-025, License Amendment Request to Revise Technical Specification 3.3.1, Reactor Trip System (RTS) Instrumentation2015-07-0909 July 2015 License Amendment Request to Revise Technical Specification 3.3.1, Reactor Trip System (RTS) Instrumentation MNS-15-026, License Amendment Request for Temporary Changes to Technical Specifications for Correction of an 'A' Train Nuclear Service Water System Degraded Condition - Drawing MCFD-2574-03.01, Rev. 11, Flow Diagram of Nuclear Service.2015-06-30030 June 2015 License Amendment Request for Temporary Changes to Technical Specifications for Correction of an 'A' Train Nuclear Service Water System Degraded Condition - Drawing MCFD-2574-03.01, Rev. 11, Flow Diagram of Nuclear Service. ML15191A0252015-06-30030 June 2015 License Amendment Request for Temporary Changes to Technical Specifications for Correction of an 'A' Train Nuclear Service Water System (Nsws) Degraded Condition ML15175A4482015-06-24024 June 2015 Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 6 of 6 ML15175A4472015-06-24024 June 2015 Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 5 of 6 ML15175A4452015-06-24024 June 2015 Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 4 of 6 ML15175A4422015-06-24024 June 2015 Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 3 of 6 2023-02-17
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BRUCE H HAMILTON Vice President t-VEnergye McGuire Nuclear Station Duke Energy Corporation MGO1 VP / 12700 Hagers Ferry Road Huntersville, NC 28078 704-875-5333 704-875-4809 fax bhhamilton@duke-energy.corn December 1, 2008 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-001
Subject:
Duke Energy Carolinas, LLC McGuire Nuclear Station, Units 1 and 2 Docket Nos. 50-369 and 50-370 Amendment to Technical Specification 3.8.1, "AC Sources-Operating," Revised Surveillance Requirements In accordance with the provisions of Section 50.90 of Title 10 of the Code of Federal Regulations (10CFR), Duke Energy Carolinas, LLC (Duke) is submitting a license amendment request (LAR) for the Renewed Facility Operating License (FOL) and Technical Specifications (TS) for McGuire Nuclear Station Units 1 and 2.The proposed amendment seeks to correct a non-conservative Technical Specification Surveillance Requirement by revising McGuire TS Surveillance Requirement (SR)3.8.1.4 to increase the minimum required amount of fuel oil for the Emergency Diesel Generators (EDG) fuel oil day tank (subsequently referred to herein as the "day tank")from 120 gallons to 39 inches of fuel oil (approximately 160 gallons) as read on the local gauge used to perform the surveillance.
A corresponding change is made to the associated TS Bases document.Attachment I provides Duke's evaluation of the LAR which contains a description of the proposed TS and associated Bases changes, the technical analysis, the determination that this LAR contains No Significant Hazards Considerations, and the basis for the categorical exclusion from performing an Environmental Assessment/Impact Statement.
Attachment 2 provides existing TS page for McGuire Units I and 2, marked-up to show the proposed changes. The associated TS Bases page affected by the proposed change is included for your information.
Reprinted (clean) TS and associated Bases pages will be provided to the NRC upon issuance of the approved amendment.
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corn December 1, 2008 Nuclear Regulatory Commission Page 2 Duke requests that NRC review and approval of this LAR be completed by December 1, 2009. Duke has determined that the NRC's standard 30-day implementation grace period will be sufficient to implement this LAR.The approval of this LAR will not require revision of the McGuire UFSAR.In accordance with Duke internal procedures and the Quality Assurance Topical Report, the proposed amendment has been reviewed and approved by the McGuire Plant Operations Review Committee and the Duke Corporate Nuclear Safety Review Board.Pursuant to 1 OCFR50.91, a copy of this LAR has been forwarded to the appropriate North Carolina state official.Please direct any questions you may have in this matter to K. L. Ashe at (704) 875-4535.Very truly yours, B. H. Hamilton I December 1, 2008 Nuclear Regulatory Commission Page 3 xc w/ Attachments:
L. A. Reyes Regional Administrator, Region II U.S. Nuclear Regulatory Commission Sam Nunn Atlanta Federal Center 61 Forsyth Street SW, Suite 23T85 Atlanta, GA 30303 J. B. Brady NRC Senior Resident Inspector McGuire Nuclear Station J. F. Stang, Jr. (addressee only)NRC Senior Project Manager (MNS and CNS)U.S. Nuclear Regulatory Commission Mail Stop 0-8 G9A Washington, DC 20555-0001 B. 0. Hall, Section Chief Division of Radiation Protection 1645 Mail Service Center Raleigh, NC 27699-1645 December 1, 2008 Nuclear Regulatory Commission Page 4 Bruce H. Hamilton affirms that he is the person who subscribed his name to the foregoing statement, and that all the matters and facts set forth herein are true and correct to the best of his knowledge.
Bruce H. Hamilton, Vice Nuclear Station Subscribed and sworn to me: (V"-KUVelbA4-lI1%cc~nrrdcY-I, 2O00LýDate , Notary Public My commission expires: O -I q-*' Date ATTACHMENT 1 EVALUATION OF PROPOSED AMENDMENT 1.0
SUMMARY
DESCRIPTION 2.0 DETAILED DESCRIPTION 3.0 TECHNICAL EVALUATION
4.0 REGULATORY EVALUATION
4.1 APPLICABLE REGULATORY REQUIREMENTS/CRITERIA 4.2 SIGNIFICANT HAZARDS CONSIDERATION
4.3 CONCLUSION
S 5.0 ENVIRONMENTAL CONSIDERATION 1.0
SUMMARY
DESCRIPTION Pursuant to 10CFR50.90, Duke Energy Carolinas, LLC (Duke) is requesting a license amendment request (LAR) for the McGuire Nuclear Station Units 1 and 2 Renewed Facility Operating Licenses (FOL) and Technical Specifications (TS). The proposed license amendment revises the McGuire Nuclear Station (MNS) Unit 1 and Unit 2 Technical Specification (TS) 3.8.1, "Electrical Power Systems, AC Sources-Operating," Surveillance Requirement (SR) 3.8.1.4.The proposed amendment seeks to correct a non-conservative Technical Specification Surveillance Requirement by revising MNS TS Surveillance Requirement (SR) 3.8.1.4 to increase the minimum required amount of fuel oil for the Emergency Diesel Generators (EDG) fuel oil day tank (subsequently referred to herein as the "day tank") from 120 gallons to 39 inches of fuel oil (as read on the local gauge used to perform the surveillance), which corresponds to approximately 160 gallons. A corresponding change is made to the associated TS Bases document.2.0 DETAILED DESCRIPTION The McGuire onsite electrical power system consists of all sources of electrical power and their associated distribution systems in each of the two generating units. These sources are the main generator, two EDGs and the batteries.
Each unit has two redundant and independent 4160 Volt Essential Auxiliary Power Systems which normally receive power from the normal power distribution system. After verification of a loss of offsite power (LOOP) or a sustained degraded offsite power condition, the normal and alternate incoming feeder circuit breakers automatically trip. During a LOOP condition, power to each of the redundant 4160 Volt Essential Auxiliary Power Systems is provided by a completely independent diesel-electric generating unit. Each of the 4160 Volt Essential Auxiliary Power System (1E) electrical buses is totally capable of fulfilling their design function independently.
There are no overlapping electrical loads shared between the 1 E buses; a loss of one EDG does not increase the demand on any other EDG.The EDG Fuel Oil System maintains a minimum supply of fuel oil onsite for four (4) EDGs, 2 engines per Unit. Each EDG has an associated fuel oil storage tank and day tank. Fuel oil is transferred from the fuel oil storage tank by the fuel oil transfer pump through the fuel oil filter to the day tank.Page 1 of 5 TS SR 3.8.1.4 currently requires that the EDG day tank contain at least 120 gallons of fuel oil, intended to be adequate for approximately 30 minutes of EDG operation at 100% load which allows for an orderly shutdown of the engine if make-up to the day tank becomes unavailable.
This 120 gallon minimum day tank volume has been determined to be inadequate.
The proposed amendment seeks to correct this non-conservative Technical Specification Surveillance Requirement by revising SR 3.8.1.4 to increase the minimum required amount of fuel oil in the day tank to approximately 160 gallons. The proposed amendment further seeks to revise the manner in which this minimal amount of fuel oil is expressed by changing (160) gallons to 39 inches of fuel oil as read on the local gauge used to perform the surveillance.
3.0 TECHNICAL EVALUATION The day tank minimum volume of 120 gallons, as currently specified in TS SR 3.8.1.4, has been determined to be inadequate to provide approximately 30 minutes of EDG operation at full load which allows for an orderly shutdown of the engine should fuel replenishment to the day tank become unavailable.
This matter was evaluated under Duke's corrective action program. As a result, McGuire has been operating under an Operable but Degraded/Non-conforming (OBDN) condition with more conservative administrative limits established for the day tank volume.Although a non-conservative Technical Specification Surveillance Requirement exists, the low level alarm (40 inches; approximately 165 gallons) and the automatic fuel transfer pump operation (43 inches;approximately 178 gallons) would have occurred prior to the day tank level descending below the 30 minute supply. Plant operators would have been made aware of a drop in day tank level and an orderly shutdown of the EDG would have begun as described in the Design Bases of the fuel system. Thus, compliance with the current TS and the licensing basis has been maintained.
The apparent cause of this non-conservatism was a lack of communication concerning the difference in requirements between McGuire Technical Specification Surveillance Requirement 3.8.1.4 and the supply of fuel calculated to meet the McGuire design basis of 30 minutes run time for the EDG. Since the discovery of this discrepancy, the Operations procedures have been revised and currently require that 39 inches of fuel oil be maintained in the EDG day tanks, which provides the mass of fuel oil required for approximately 30 minutes of EDG operation at 100% load and an additional allowance for instrument uncertainty and potential vortex formation.
Page 2 of 5 Calculations for EDG fuel oil usage conservatively assumed the lowest specific gravity allowed by the Diesel Generator Fuel Oil Testing Program.Thus, these calculations account for the varying heat content/consumption based on the worst case fuel oil quality allowed by Technical Specification.
Although the proposed change deviates from NUREG 1431, SR 3.8.1.4 (i.e., expression of fuel oil quantity as inches vs gallons), it is more appropriate to state the fuel oil requirement in "inches" of indicated level since this is consistent with the configuration of the instrumentation installed on the EDG day tank.
4.0 REGULATORY EVALUATION
4.1 Applicable Regulatory Requirements/Criteria:
As required by General Design Criteria (GDC) 17, an onsite electric power system shall be provided to permit functioning of structures, systems and components important to safety. The emergency diesel generators (EDG) satisfy the requirements of GDC 17. The Fuel Oil System supplies fuel oil to the EDGs. The day tank supplies sufficient capacity to successfully start the EDG and allow for the orderly shutdown of the EDG in the event of a loss of fuel from the fuel oil storage tank or a fuel oil transfer pump problem. The proposed change to SR 3.8.1.4 is conservative in nature and has been determined to have no adverse impact on the EDGs ability to fulfill their design basis function as required by 10 CFR 50, Appendix A, GDC-17.4.2 Significant Hazards Consideration:
The proposed amendment seeks to correct a non-conservative Technical Specification Surveillance Requirement by revising MNS TS Surveillance Requirement (SR) 3.8.1.4 to increase the minimum required amount of fuel oil for the Emergency Diesel Generators (EDG)fuel oil day tank from 120 gallons to 39 inches of fuel oil (as read on the local gauge used to perform the surveillance), which corresponds to approximately 160 gallons. A corresponding change is made to the associated TS Bases document.Duke Energy Carolinas, LLC (Duke) has concluded that operation of McGuire Nuclear Station (MNS) Units 1 & 2, in accordance with the proposed changes to the Technical Specifications (TS) does not involve a significant hazards consideration.
Duke's conclusion is based on its evaluation, in accordance with 10 CFR 50.91 (a)(I), of the three standards set forth in 10 CFR 50.92(c) as discussed below: Page 3 of 5 A. Does the proposed amendment involve a significant increase in the probability or consequences of an accident previously evaluated?
Response:
No.Implementation of the proposed amendment does not significantly increase the probability or the consequences of an accident previously evaluated.
The Emergency Diesel Generators (EDGs)and their associated emergency buses function as accident mitigators.
The proposed changes do not involve a change in the operational limits or the design of the electrical power systems (particularly the emergency power systems) or change the function or operation of plant equipment or affect the response of that equipment when called upon to operate.The proposed change to TS SR 3.8.1.4 confirms the minimum supply of fuel oil in the emergency diesel generators (EDG) fuel oil day tank. The minimum value for the affected parameter is being increased in the conservative direction and further ensures the EDGs ability to fulfill their safety related function.Thus, based on the above, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
B. Does the proposed amendment create the possibility of a new or different kind of accident from any accident previously evaluated?
Response:
No.The proposed changes do not involve a change in the operational limits or the design capabilities of the emergency electrical power systems. The proposed changes do not change the function or operation of plant equipment or introduce any new failure mechanisms.
The evaluation that supports this LAR included a review of the EDG fuel oil system to which this parameter applies.The proposed changes do not introduce any new or different types of failure mechanisms; plant equipment will continue to respond as designed and analyzed.C. Does the proposed amendment involve a significant reduction in the margin of safety?Response:
No.Page 4 of 5 Margin of safety is related to the confidence in the ability of the fission product barriers to perform their design functions during and following an accident situation.
These barriers include the fuel cladding, the reactor coolant system, and the containment system.The performance of the fuel cladding, the reactor coolant system and the containment system will not be adversely impacted by the proposed changes.Thus, it is concluded that the proposed TS and TS Bases changes do not involve a significant reduction in the margin of safety.4.3
Conclusions:
The proposed amendment seeks to correct a non-conservative Technical Specification Surveillance Requirement by revising MNS TS Surveillance Requirement (SR) 3.8.1.4 to increase the minimum required amount of fuel oil for the Emergency Diesel Generators (EDG)fuel oil day tank from 120 gallons to 39 inches of fuel oil (corresponding to approximately 160 gallons).The proposed changes do not involve a change in the operational limits or the design capabilities of the emergency electrical power systems. The proposed changes do not change the function or operation of plant equipment or introduce any new failure mechanisms.
The ability to successfully start and allow for the orderly shutdown of the EDG in the event of a loss of fuel from the fuel oil storage tank or a fuel oil transfer pump problem will be improved by the proposed amendment.
5.0 ENVIRONMENTAL CONSIDERATION The proposed change does not involve a significant hazards consideration, a significant change in the types of or significant increase in the amounts of any effluents that may be released offsite, or a significant increase in individual or cumulative occupational radiation exposure.Therefore, the proposed change meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Pursuant to 10 CFR 51.22(b), an environmental assessment of the proposed change is not required.Page 5 of 5 ATTACHMENT 2 MARKED PAGES OF AFFECTED McGUIRE TECHNICAL SPECIlFICATIONS AND ASSOCIATED BASES AC Sources -Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY+SR 3.8.1.3-------------------
NOTES -------------
- 1. DG loadings may include gradual loading as recommended by the manufacturer.
- 2. Momentary transients outside the load range do not invalidate this test.3. This Surveillance shall be conducted on only one DG at a time.4. This SR shall be preceded by and immediately follow without shutdown a successful performance of SR 3.8.1.2 or SR 3.8.1.7.Verify each DG is synchronized and loaded and operates for >_ 60 minutes at a load _> 3600 kW and < 4000 kW.31 days SR 3.8.1.4 Verify each day tank contains> --ga 9 chesffuel 31 days oil.SR 3.8.1.5 Check for and remove accumulated water from each day 31 days tank.SR 3.8.1.6 Verify the fuel oil transfer system operates to 31 days automatically transfer fuel oil from storage tank to the day tank.(continued)
McGuire Units 1 and 2 3.8.1-6 Amendment Nos.
AC Sources-Operating B 3.8.1 BASES SURVEILLANCE REQUIREMENTS (continued)
SR 3.8.1.4 This SR provides verification that the level of fuel oil in the day tank is at a oxmately 30 minutes of DG operplna ul odhich allows for an orderly bs the leltDG suhou tomtic to the day tank //be o e unavailabl.-e._
l -The 31 day Frequency is adequate to assure that a sufficient supply of fuel oil is available, since low level alarms are provided and facility operators would be aware of any large uses of fuel oil during this period.SR 3.8.1.5 Microbiological fouling is a major cause of fuel oil degradation.
There are numerous bacteria that can grow in fuel oil and cause fouling, but all must have a water environment in order to survive. Removal of water from the fuel oil day tanks once every 31 days eliminates the necessary environment for bacterial survival.
This is the most effective means of controlling microbiological fouling. In addition, it eliminates the potential for water entrainment in the fuel oil during DG operation.
Water may come from any of several sources, including condensation, ground water, rain water, contaminated fuel oil, and breakdown of the fuel oil by bacteria.
Frequent checking for and removal of accumulated water minimizes fouling and provides data regarding the watertight integrity of the fuel oil system. The Surveillance Frequencies are established by Regulatory Guide 1.137 (Ref. 11). This SR is for preventative maintenance.
The presence of water does not necessarily represent failure of this SR, provided the accumulated water is removed during the performance of this Surveillance.
SR 3.8.1.6 This Surveillance demonstrates that each required fuel oil transfer pump operates and transfers fuel oil from its associated storage tank to its associated day tank. This is required to support continuous operation of standby power sources. This Surveillance provides assurance that the fuel oil transfer pump is OPERABLE, the fuel oil piping system is intact, the fuel delivery piping is not obstructed, and the controls and control systems for automatic fuel transfer systems are OPERABLE.The design of fuel transfer systems is such that pumps operate automatically or may be started manually in order to maintain an McGuire Units 1 and 2 B 3.8.1-17 Revision No.