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Category:Memoranda
MONTHYEARML24124A0342024-05-0101 May 2024 Summary of Public Meeting Concerning Annual Assessment of Catawba Nuclear Station Units 1 and 2, McGuire Nuclear Station Units 1 and 2, Oconee Nuclear Station Units 1, 2, and 3, Brunswick Steam Electric Plant Units 1 and 2, Shearon Harris ML24047A2092024-02-22022 February 2024 Calendar Year 2023 Baseline Inspection Completion ML23118A2852023-05-0202 May 2023 Public Meeting Summary - 2022 Annual Assessment Meeting Regarding Catawba Nuclear Station, McGuire Nuclear and Oconee Nuclear Station ML22299A1052023-01-11011 January 2023 Memo to File - McGuire Final EA 2017+19+21 ML21056A5502021-04-22022 April 2021 Memo to File - Ea/Fonsi for McGuire DFP ML21099A0932021-04-0909 April 2021 Public Meeting Summary - 2020 Annual Assessment Meeting Regarding Catawba, McGuire, and Oconee Nuclear Stations ML20141L4172020-05-20020 May 2020 EOC Public Meeting Summary ML19088A1362019-03-29029 March 2019 Public Meeting Summary ML20052D9362018-07-0303 July 2018 Response to Nrg Request for Additional Information (RAI) Regarding NAC Magnastor Cask Loaded to Incorrect Helium Backfill Density ML18089A0532018-03-30030 March 2018 Summary of Public Meeting with McGuire Nuclear Station ML17151A3372017-06-0202 June 2017 Recommendation for Non-Acceptance with Opportunity to Supplement of McGuire Nuclear Station Units 1 and 2 Technical Specifications Completion Time Extension Request for Failure to Supply Information (CACs MF9673, MF9674) ML17110A1862017-04-20020 April 2017 Summary of Public Meeting - McGuire, Units 1 and 2 to Discuss Concerning Annual Assessment ML16088A2042016-03-28028 March 2016 Memo T Bowers from s Ruffin, Technical Assistance Requests - Review 2015 Tri-Annual Decommissioning Funding Plans for Multiple Independent Spent Fuel Storage Installations W/ Encl 2 (Template) ML16088A2052016-03-28028 March 2016 Enclosure 1 - (72.30 DFP Reviews to Be Completed 2015) - Memo T Bowers from s Ruffin, Technial Assistance Requests - Review 2015 Tri-Annual Decommissioning Funding Plans for Multiple Independent Spent Fuel Storage Installations ML16082A0682016-03-21021 March 2016 Summary of Meeting with the Public Concerning the Annual Assessment of McGuire Nuclear Station, Units 1 and 2 ML15138A3392015-06-0101 June 2015 Summary of Public Teleconference Regarding Potential Submission of a License Amendment Request for a One-Time Extension of Completion Time for Nuclear Service Water System ML15106A0222015-04-15015 April 2015 Summary of Meeting with Public to Discuss Annual Assessment of McGuire Nuclear Station, Units 1 and 2, in Huntersville, North Carolina ML15119A2182015-04-0707 April 2015 Technical Specification (TS) and Tech Spec Bases (Tsb) Manual ML15083A0832015-03-10010 March 2015 TS Bases Updates ML14136A1302014-05-15015 May 2014 End of Cycle Meeting Summary Memo ML14142A0112014-05-0505 May 2014 Technical Specification & Technical Specification Bases ML13295A3062013-10-22022 October 2013 Meeting Notice with Duke Energy Carolinas, LLC Discuss the Planned Modifications Related to the Fukushima Flood Hazard Reevaluations for the Sites Operated by Duke Energy Carolinas, LLC ML13198A1732013-07-17017 July 2013 Notice of Forthcoming Pre-Application Teleconference with Duke Energy Carolinas, LLC, McGuire Units 1 and 2 ML13191A9592013-07-15015 July 2013 Notice of Pre-Application Meeting with Duke Energy Carolinas, LLC, McGuire Units 1 & 2, to Discuss with Licensee Its Proposed License Amendment Request to Technical Specification 3.8.4 Condition a to Allow Replacement of Existing Shared ... ML13204A1162013-06-26026 June 2013 SLC Manual Update ML13135A5962013-05-16016 May 2013 Cancelled 05/23/2013 Notice of Forthcoming Pre-Application Meeting with Duke Energy Carolinas, Llc. to Discuss a Proposed License Amendment Request Concerning Methodology Report DPC-NE-3001-P for Catawba and McGuire Nuclear Stations ML13127A4352013-05-0909 May 2013 Notice of Forthcoming Pre-Application Meeting with Duke Energy Carolinas, Llc. to Discuss a Proposed License Amendment Request Concerning Methodology Report DPC-NE-3001-P for Catawba and McGuire Nuclear Stations ML13072B2022013-03-19019 March 2013 Meeting Notice with Duke Energy Concerning NFPA-805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants License Amendment Request for Catawba, McGuire, and H. B. Robinson ML12340A5182012-11-26026 November 2012 Submittal of Technical Specification (TS) and Technical Specification Bases (Tsb) Manual ML12300A4032012-10-26026 October 2012 11/8/2012 Meeting Notice with Duke Energy to Discuss NRC Order on Mitigation Strategies for Beyond-design-Basis External Events ML12284A4612012-10-12012 October 2012 Forthcoming Meeting Notice with Duke Energy to Discuss NRC Order on Mitigation Strategies for Beyond-Design-Basis External Events ML1218006502012-07-0303 July 2012 Mcguire Nuclear Station, Units 1 and 2 - Fire Protection Fire Protection Safety Evaluation Input Regarding License Amendment Request Measurement Uncertainty Recapture Power Uprate ML11257A0382011-09-0101 September 2011 Technical Specification Bases Updates ML1106603302011-03-0707 March 2011 Notice of Meeting with Duke Energy to Present Status of Licensing Submittals Regarding Implementation of National Fire Protection Association Standard 805, Requirements at Catawba Nuclear Station, Units 1 and 2 and McGuire Nuclear Station ML1104900602011-03-0404 March 2011 Final McGuire Task Interface Agreement (TIA) - McGuire Service Water System Unit Crossties Relative to Sharing/Donating in Abnormal Procedures (TIA 2009-011) ML1029306502010-10-20020 October 2010 Notice of Forthcoming Conference Call with Duke Energy Carolinas, LLC Regarding McGuire Nuclear Station, Units 1 and 2 and Catawba Nuclear Station, Units 1 and 2, ML1027001972010-09-14014 September 2010 Revisions to Technical Specifications Bases ML1025203282010-09-13013 September 2010 Notice of Forthcoming Conference Call with Duke Energy Carolinas, LLC (Duke), to Discuss Duke'S Potential Submittal of an Amendment to McGuire 1 and 2 Licenses Regarding Implementation of an Alternate Source Term ML1015804072010-06-0808 June 2010 the Nuclear Regulatory Commission Staff Spot-Check Review of Duke Energy'S Ownership Interest of Catawba, Units 1 and 2, McGuire, Units 1 and 2, and Oconee, Units 1, 2 and 3 on May 20, 2010 - Finding of No Potential Issues in Bank Statement ML1012604632010-05-0707 May 2010 Notice of Forthcoming Conference Call with Duke Energy Carolinas, LLC (Duke) to Discuss Duke'S Responses to Generic Letter 2004-02 at Catawba 1 and 2 and McGuire 1 and 2 ML1007503442010-03-10010 March 2010 Submittal of Technical Specification Bases Updates ML0926700202009-10-0707 October 2009 Summary of Conference Call with Duke Regarding Responses to Generic Letter (GL) 2004-02 ML0922908922009-08-18018 August 2009 Notice of Conference Call with Duke Energy Carolinas, LLC (Duke), Regarding Catawba Nuclear Station, Units 1 and 2 (Catawba 1 and 2) and McGuire Nuclear Station Units 1 and 2 ML0908202662009-03-16016 March 2009 Submittal of Facility Operating License Revision ML0831009482008-11-10010 November 2008 Notice of Meeting with Duke Energy Carolinas, LLC, (Duke), Catawba, Units 1 and 2, and McGuire, Units 1 and 2 ML0831107952008-11-0606 November 2008 Cancellation of Meeting with Duke Energy Carolinas, LLC, to Discuss the Request for Additional Information Generic Letter 2004-04, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents. ML0829701832008-10-30030 October 2008 Notice of Meeting with Duke Energy Carolinas, LLC, to Discuss the Request for Additional Information Generic Letter 2004-04, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents ... ML0818301542008-07-0101 July 2008 Notice of Meeting with Duke Energy Carolinas, LLC to Discuss Transition to ASME NQA-1-1994 ML0809200162008-04-0101 April 2008 Notice of Forthcoming Meeting with Petitioner Requesting Action Under 10 CFR 2.2.06 Regarding Protection Against High-Pressure Feedwater Heater ML0807400842008-03-14014 March 2008 Draft Regulatory Guide for Comment 2024-05-01
[Table view] Category:Technical Specification
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-18-0190, 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-22-0080, Independent Spent Fuel Storage Installation, McGuire, Units 1 & 2, Independent Spent Fuel Storage Installation, Request for an Exemption to the Requirements of Certificate of Compliance No. 1031 for the NAC Magnastor Storage System2022-04-0707 April 2022 Independent Spent Fuel Storage Installation, McGuire, Units 1 & 2, Independent Spent Fuel Storage Installation, Request for an Exemption to the Requirements of Certificate of Compliance No. 1031 for the NAC Magnastor Storage System 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-21-0027, Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2021-09-16016 September 2021 Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections RA-20-0207, Duke Energy - Application to Revise the Technical Specification for Engineered Safety Feature Actuation System (ESFAS) Instrumentation2020-12-0303 December 2020 Duke Energy - Application to Revise the Technical Specification for Engineered Safety Feature Actuation System (ESFAS) Instrumentation 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-18-0232, Proposed Editorial Error Correction of Technical Specification (TS) 3.0, Surveillance Requirement Applicability, SR 3.0.5 and Proposed Removal of Expired TS Footnotes from the MNS2019-02-0505 February 2019 Proposed Editorial Error Correction of Technical Specification (TS) 3.0, Surveillance Requirement Applicability, SR 3.0.5 and Proposed Removal of Expired TS Footnotes from the MNS RA-18-0166, Supplement to Non-Voluntary License Amendment Request (LAR) to Correct Non-Conservative Technical Specification 3.4.11 - PORVs2018-09-13013 September 2018 Supplement to Non-Voluntary License Amendment Request (LAR) to Correct Non-Conservative Technical Specification 3.4.11 - PORVs ML18191A5452018-07-10010 July 2018 Attachment 2 - McGuire Technical Specification 3.8.1 Bases Marked Up Pages RA-18-001, Attachment 2 - McGuire Technical Specification 3.8.1 Bases Marked Up Pages2018-07-10010 July 2018 Attachment 2 - McGuire Technical Specification 3.8.1 Bases Marked Up Pages 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 RA-18-0001, Duke Energy Progress, LLC and Duke Energy Carolinas, LLC - License Amendment Application to Remove Heaters from Ventilation System Technical Specifications2018-05-10010 May 2018 Duke Energy Progress, LLC and Duke Energy Carolinas, LLC - License Amendment Application to Remove Heaters from Ventilation System Technical Specifications 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-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 RA-17-0045, Supplement: Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules.2017-10-12012 October 2017 Supplement: Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules. ML17237A0492017-08-17017 August 2017 Technical Specification Bases - List of Effected Sheets ML17237A0482017-08-17017 August 2017 Technical Specification Bases (Rev. 150) ML17237A0462017-08-17017 August 2017 Document Transmittal Form Regarding Technical Specification Changes - Amendment Nos. 296/275 ML17186A0682017-06-26026 June 2017 Tech Spec Bases - List of Affected Sections ML17186A0672017-06-26026 June 2017 Revision 151 to Tech Spec Bases - B 3.6.13 and B 3.6.14 ML17186A0662017-06-26026 June 2017 TS 3.6.13 Amendment 292/271 and TS 3.6.14 Amendment 294/273 ML17186A0692017-06-26026 June 2017 Issue Tech Spec - List of Affected Pages ML17136A2792017-05-0303 May 2017 Technical Specification Leep, Rev. 109 ML17136A2782017-05-0303 May 2017 Technical Specification Bases - Loes, Rev. 133 ML17136A3612017-05-0303 May 2017 Technical Specification Bases, Revision 149 ML17136A3602017-05-0303 May 2017 Technical Specification Amendment Nos. 285/264 ML17124A3682017-04-19019 April 2017 Tech Spec Bases List of Effected Pages ML17124A3712017-04-19019 April 2017 Bases B 3.5.1 - Accumulators ML17094A6722017-03-29029 March 2017 Issue Selected License Commitment Cslcl 16.7.14 Revision ML17094A6732017-03-29029 March 2017 Issue SLC List of Effected Pages ML17090A4522017-03-23023 March 2017 Revision to Technical Specification 3.3.2 - Amendment 293/272 ML17090A4512017-03-23023 March 2017 Revision to Technical Specification 3.8.1 - Amendment 293/272 ML17090A4352017-03-22022 March 2017 Technical Specification Bases ML17090A4502017-03-22022 March 2017 Revision to Technical Specification Bases - B 3.6.15 ML17094A6702017-03-15015 March 2017 Issue MNS-SLC-16.9.15. Snubbers 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 ML16305A1442016-10-20020 October 2016 Issue MNS Technical Specification 5.5 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 ML16265A5312016-08-30030 August 2016 Issue MNS Tech Spec Bases List of Effective Sections ML16265A5322016-08-30030 August 2016 Technical Specification Bases 3.6.14 Revisions, List of Revisions and Dates ML16250A0142016-08-29029 August 2016 Amendment 287 ML16243A3492016-08-23023 August 2016 Mccguire, Units 1 and 2, Revision 143 to Issue MNS Technical Specification Bases 3.3.1 ML16243A3482016-08-23023 August 2016 Technical Specification 3.3.1, Reactor Trip System (RTS) Instrumentation. ML16243A3512016-08-23023 August 2016 Revision 105 to Technical Specifications List of Effective Pages ML16243A3502016-08-23023 August 2016 Revision 129 to Technical Specification Bases ML16243A3572016-08-18018 August 2016 Technical Specification Bases Revision 001, List of Revised Sections 2023-02-16
[Table view] Category:Bases Change
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-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-18-0232, Proposed Editorial Error Correction of Technical Specification (TS) 3.0, Surveillance Requirement Applicability, SR 3.0.5 and Proposed Removal of Expired TS Footnotes from the MNS2019-02-0505 February 2019 Proposed Editorial Error Correction of Technical Specification (TS) 3.0, Surveillance Requirement Applicability, SR 3.0.5 and Proposed Removal of Expired TS Footnotes from the MNS RA-18-0166, Supplement to Non-Voluntary License Amendment Request (LAR) to Correct Non-Conservative Technical Specification 3.4.11 - PORVs2018-09-13013 September 2018 Supplement to Non-Voluntary License Amendment Request (LAR) to Correct Non-Conservative Technical Specification 3.4.11 - PORVs ML18191A5452018-07-10010 July 2018 Attachment 2 - McGuire Technical Specification 3.8.1 Bases Marked Up Pages RA-18-001, Attachment 2 - McGuire Technical Specification 3.8.1 Bases Marked Up Pages2018-07-10010 July 2018 Attachment 2 - McGuire Technical Specification 3.8.1 Bases Marked Up Pages RA-17-0045, Supplement: Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules.2017-10-12012 October 2017 Supplement: Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules. ML17237A0462017-08-17017 August 2017 Document Transmittal Form Regarding Technical Specification Changes - Amendment Nos. 296/275 ML17237A0482017-08-17017 August 2017 Technical Specification Bases (Rev. 150) ML17237A0492017-08-17017 August 2017 Technical Specification Bases - List of Effected Sheets ML17186A0662017-06-26026 June 2017 TS 3.6.13 Amendment 292/271 and TS 3.6.14 Amendment 294/273 ML17186A0672017-06-26026 June 2017 Revision 151 to Tech Spec Bases - B 3.6.13 and B 3.6.14 ML17186A0682017-06-26026 June 2017 Tech Spec Bases - List of Affected Sections ML17186A0692017-06-26026 June 2017 Issue Tech Spec - List of Affected Pages ML17136A3612017-05-0303 May 2017 Technical Specification Bases, Revision 149 ML17136A3602017-05-0303 May 2017 Technical Specification Amendment Nos. 285/264 ML17136A2792017-05-0303 May 2017 Technical Specification Leep, Rev. 109 ML17136A2782017-05-0303 May 2017 Technical Specification Bases - Loes, Rev. 133 ML17124A3682017-04-19019 April 2017 Tech Spec Bases List of Effected Pages ML17124A3712017-04-19019 April 2017 Bases B 3.5.1 - Accumulators ML17094A6722017-03-29029 March 2017 Issue Selected License Commitment Cslcl 16.7.14 Revision ML17094A6732017-03-29029 March 2017 Issue SLC List of Effected Pages ML17090A4522017-03-23023 March 2017 Revision to Technical Specification 3.3.2 - Amendment 293/272 ML17090A4512017-03-23023 March 2017 Revision to Technical Specification 3.8.1 - Amendment 293/272 ML17090A4352017-03-22022 March 2017 Technical Specification Bases ML17090A4502017-03-22022 March 2017 Revision to Technical Specification Bases - B 3.6.15 ML17094A6702017-03-15015 March 2017 Issue MNS-SLC-16.9.15. Snubbers 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 ML16265A5312016-08-30030 August 2016 Issue MNS Tech Spec Bases List of Effective Sections ML16265A5322016-08-30030 August 2016 Technical Specification Bases 3.6.14 Revisions, List of Revisions and Dates ML16250A0142016-08-29029 August 2016 Amendment 287 ML16243A3482016-08-23023 August 2016 Technical Specification 3.3.1, Reactor Trip System (RTS) Instrumentation. ML16243A3502016-08-23023 August 2016 Revision 129 to Technical Specification Bases ML16243A3512016-08-23023 August 2016 Revision 105 to Technical Specifications List of Effective Pages ML16243A3492016-08-23023 August 2016 Mccguire, Units 1 and 2, Revision 143 to Issue MNS Technical Specification Bases 3.3.1 ML16243A3572016-08-18018 August 2016 Technical Specification Bases Revision 001, List of Revised Sections ML16243A3552016-08-17017 August 2016 Renewed Facility Operating License, Amendment 284 ML16243A3522016-08-17017 August 2016 Technical Specification 3.4.18, Amendment Nos. 284/263, Steam Generator (SG) Tube Integrity. ML16243A3542016-08-17017 August 2016 Technical Specification Bases 3.4.18, Revision 144, Steam Generator (SG) Tube Integrity RA-16-0007, Duke Energy Carolinas, LLC, Application to Revise TS to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability Using the Consolidated Line Item Improvement Process2016-06-23023 June 2016 Duke Energy Carolinas, LLC, Application to Revise TS to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability Using the Consolidated Line Item Improvement Process ML16139A5572016-05-10010 May 2016 Technical Specification Bases 3.3.1 Rev. 001, Revision 141 ML16139A5552016-05-10010 May 2016 Technical Specification Bases 3.9.3, Revision 001, Revision 142 MNS-16-020, License Amendment Request Removal of Superseded Technical Specification Requirements2016-05-0505 May 2016 License Amendment Request Removal of Superseded Technical Specification Requirements 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 ML16056A2432016-02-18018 February 2016 Emergency Action Level Technical Bases Document Redline MNS-16-016, Emergency Action Level Technical Bases, Revision 1 Redline. Part 1 of 22016-02-18018 February 2016 Emergency Action Level Technical Bases, Revision 1 Redline. Part 1 of 2 ML16056A2452016-02-18018 February 2016 Emergency Action Level Technical Bases, Revision 1 Redline. Part 2 of 2 2023-02-16
[Table view] Category:Technical Specifications
MONTHYEARML24052A3062024-04-0808 April 2024 Issuance of Amendment Nos. 331 & 310, Regarding Adoption of Title 10 of Code of Federal Regulations Section 50.69, “Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Plants ML24031A5402024-03-26026 March 2024 Issuance of Amendment Nos. 330 and 309 Regarding Implementation of TSTF 505,Rev. 2, “Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4B ML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 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 ML18355A6102019-01-25025 January 2019 Issuance of Amendments to Revise the Licensing Basis for Protection from Tornado Generated Missiles ML18318A3582019-01-16016 January 2019 Issuance of Amendment Nos. 311 and 290 to Correct Non-Conservative Technical Specification 3.4.11, Pressurizer Power Operated Relief Valves Porvs) RA-17-0051, Supplement to License Amendment Request Proposing Changes to Catawba and McGuire Technical Specification 3.8.1, AC Sources - Operating2017-11-21021 November 2017 Supplement to License Amendment Request Proposing Changes to Catawba and McGuire Technical Specification 3.8.1, AC Sources - Operating ML17269A0552017-10-25025 October 2017 McGuire, Units 1 and 2 - Issuance of Amendments Adopting Technical Specification Task Force Traveler TSTF-283-A, Revision 3 (CAC NOS. MF9098 and MF9099) ML17248A4692017-08-29029 August 2017 Tech Spec and Tech Spec Bases TS-LOEP & TSB-LOES ML17237A0472017-08-17017 August 2017 Document Transmittal Form Regarding Technical Specification - List of Effected Pages (Rev. 111) 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 ML17066A3742017-04-26026 April 2017 Issuance of Amendments Re. Application to Revise TSs to Adopt TSTF-427, Rev. 2, Using the Consolidated Line Item Improvement Process (CAC Nos. MF8039 Through MF8049) ML17087A2732017-03-22022 March 2017 Issue Tech Specification List of Affected Pages (Loep), Revision 108 ML17087A2722017-03-22022 March 2017 Renewed Facility Operating License - Amendment 293 ML16236A0532016-09-26026 September 2016 Issuance of Amendments Regarding One-Time Extension of Appendix J Type a Integrated Leakage Rate Test Interval ML16243A3532016-08-17017 August 2016 Technical Specifications 5.5, Revision 1 - Amendment No. 276/256 ML16139A4612016-05-10010 May 2016 Technical Specification 3.3.1, Rev. 001, Amendments 283 and 262 ML16075A3012016-04-26026 April 2016 Issuance of Amendments Regarding the Revision of the Steam Generator Technical Specifications to Reflect the Adoption of TSTF-510(CAC Nos. MF6139,MF6140,MF6141,MF6142,MF6143,MF6144. ML16067A2292016-04-0808 April 2016 Issuance of Amendments Regarding Removal of Obsolete Technical Specification Requirements 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. ML15306A1412016-03-16016 March 2016 Issuance of License Amendment Regarding Nuclear Service Water System Allowed Outrage Time Extension ML16004A3522016-02-0303 February 2016 Issuance of Amendment Request to Revise Technical Specification for Residual Heat Removal System Air Handler Unit 1 ML15174A1732015-08-24024 August 2015 Issuance of Amendments Regarding Technical Specification Definition of Rated Thermal Power ML15133A4532015-06-11011 June 2015 McGuire Nuclear Station, Oconee Nuclear Station - Issuance of Amendments Regarding Changes to Cyber Security Plan Implementation Schedule Milestone 8 ML15063A2712015-04-14014 April 2015 Issuance of Amendments Technical Specification 3.1.3, Moderator Temperature Coefficient and TS 5.6.5, Core Operating Limits Report. ML15119A2182015-04-0707 April 2015 Technical Specification (TS) and Tech Spec Bases (Tsb) Manual ML15027A3662015-03-25025 March 2015 Issuance of Amendments DPC-NE-3001-P, Multidimensional Reactor Transients and Safety Analysis Physics Parameters Methodology MNS-15-013, Submits a License Amendment Request for the Renewed Facility Operating Licenses and Technical Specifications to Remove a Superseded TS Requirement2015-03-23023 March 2015 Submits a License Amendment Request for the Renewed Facility Operating Licenses and Technical Specifications to Remove a Superseded TS Requirement ML15002A3242015-02-12012 February 2015 McGuire Nuclear Station, and Oconee Nuclear Station - Issuance of Amendments Regarding Changes to Organization, Unit Staff Responsibility, Unit Staff Qualifications, Programs and Manuals, and High Radiation Areas ML14231A6342014-09-10010 September 2014 Issuance of Amendments Regarding Technical Specification 3.8.4, DC Sources-Operating, ML14211A4032014-08-27027 August 2014 Issuance of Amendments Regarding Technical Specification 3.3.2 in Support of Compliance with NRC Order EA-12-049 ML14142A0112014-05-0505 May 2014 Technical Specification & Technical Specification Bases ML13316A0072013-10-31031 October 2013 Updated Technical Specifications Manual and Bases ML13277A3602013-09-24024 September 2013 Technical Specifications Bases ML13135A1332013-04-25025 April 2013 Annual Radioactive Effluent Release Report ML12340A4062012-11-27027 November 2012 Technical Specifications & Technical Specification Bases Updates. Includes Tsb Loes (Revision 114) & Tsb 3.6.15 (Entire Section) Rev 125 ML12240A1962012-09-29029 September 2012 Issuance of Amendments, Regarding Changes to Diesel Generator Starting Air Pressure Limits ML12229A1462012-08-0909 August 2012 License Amendment Request for One-Time Change to Technical Specification 3.8.4, DC Sources-Operating for Battery Replacement ML12082A2102012-03-0505 March 2012 License Amendment Request for Measurement Uncertainty Recapture Power Uprate ML11341A1102011-12-0505 December 2011 License Amendment Request for Changes to Technical Specification Table 3.3.1-1, Reactor Trip System Instrumentation, Function 16(e) ML11318A1172011-11-0909 November 2011 License Amendment Request for Temporary Changes to Technical Specifications and Limited Duration Use of NUREG-0800, Section 3.5.1.3, Revision 3, to Allow Nuclear Service Water System (Nsws) 'A' Train Repair ML11131A1332011-09-12012 September 2011 License Amendment, Issuance of Amendments Regarding Technical Specification Changes to Allow Manual Operation of the Containment Spray System ML11140A0882011-05-12012 May 2011 Request for Exemption from Certain Requirements of 10 CFR 72.212(a)(2), 72.212(b)(2)(i), 72.212(b)(7) and 72.214 ML1106603442011-02-28028 February 2011 Technical Specification and Tec Spec Bases Updates ML1103200662011-01-24024 January 2011 Notice of Enforcement Discretion Request (Noed), Technical Specification (TS) Limiting Condition for Operation (LCO) 3.0.3 ML1032700962010-12-20020 December 2010 License Amendment, Issuance of Amendments Regarding Revision of Technical Specification (TS) 3.8.4 DC (Direct Current) Sources - Operating. ML1032706582010-11-18018 November 2010 Response to Request for Additional Information to Application for Technical Specification Change Re Risk-Informed Justification for Relocation of Specific Surveillance Frequency Requirements ML1022803352010-08-0404 August 2010 Technical Specification Updates ML1019504512010-08-0202 August 2010 Issuance of Amendments Regarding Replacement of Source Range and Intermediate Range Encore Detection Systems with Equivalent Neutron Monitoring Systems Using Fission Chamber Detectors (TAC ME1749 & ME1750) ML1021503242010-06-28028 June 2010 Technical Specifications and Technical Specifications Bases Updates 2024-04-08
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DISPOSITION OF THE ORIGINAL DOCUMENT WILL BE TO PRIORITY Normal THE TRANSMITTAL SIGNATURE UNLESS RECIPIENT IS Date: 05/05/14 OTHERWISE IDENTIFIED BELOW Document Transmittal #: DUK141250019
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DOCUMENT NO QA COND REV #/ DATE DISTR CODE 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 TOTAL TSB 3.6.9 NA 131 04/14/14 MADM-04B V1 V1 V1 x Vl V3 V1 V1 V1 V1 V1 V1 V1 29 T.S.B 3.6.16 NA 130 04/07/14
- ________ A ____________________________ A ___ .1___ +/- ___ L ___ L ___ .1___ +/- ___ £ ___ I ___ A ____ L ___ L ___ ___
REMARKS: PLEASE UPDATE ACCORDINGLY.
S D CAPPS LOES REVISION 119 DATED 04/21/2014 VICE PRESIDENT MCGUIRE NUCLEAR STATION BY:
BC BEAVER MGO1RC BCB/BRG
April 21, 2014 MEMORANDUM To: All McGuire Nuclear Station Technical Specification (TS) and Tech Spec Bases (TSB) Manual Holders
Subject:
McGuire TS and TSB Updates REMOVE INSERT TS Bases Manual LOES (rev 118) LOES (rev 119)
TSB 3.6.9 Rev 115 (entire section) TSB 3.6.9 Rev 131 (entire section)
TSB 3.6.16 Rev 115 (entire section) TSB 3.6.16 Rev 130 (entire section)
Revision numbers may skip numbers due to Regulatory Compliance Filing System.
Please call me if you have questions.
Bonnie Beaver Regulatory Compliance 875-4180
McGuire Nuclear Station Technical Specification Bases LOES TS Bases are revised by section Page Number Revision Revision Date BASES (Revised per section) i Revision 87 8/15/07 ii Revision 87 8/15/07 iii Revision 87 8/15/07 B 2.1.1 Revision 51 01/14/04 B 2.1.2 Revision 109 9/20/10 B 3.0 Revision 81 3/29/07 B 3.1.1 Revision 115 3/29/11 B 3.1.2 Revision 115 3/29/11 B 3.1.3 Revision 10 9/22/00 B 3.1.4 Revision 115 3/29/11 B 3.1.5 Revision 115 3/29/11 B 3.1.6 Revision 115 3/29/11 B 3.1.7 Revision 58 06/23/04 B 3.1.8 Revision 115 3/29/11 B 3.2.1 Revision 115 3/29/11 B 3.2.2 Revision 115 3/29/11 B 3.2.3 Revision 115 3/29/11 B 3.2.4 Revision 115 3/29/11 B 3.3.1 Revision 124 10/1/12 B 3.3.2 Revision 122 10/25/12 B 3.3.3 Revision 122 10/25/12 B 3.3.4 Revision 115 3/29/11 B 3.3.5 Revision 115 3/29/11 B 3.3.6 Not Used - Revision 87 6/29/06 B 3.4.1 Revision 115 3/29/11 B 3.4.2 Revision 0 9/30/98 B 3.4.3 Revision 115 3/29/11 B 3.4.4 Revision 115 3/29/11 B 3.4.5 Revision 115 3/29/11 McGuire Units 1 and 2 Page I Revision 119
Page Number Amendment Revision Date B 3.4.6 Revision 115 3/29/11 B 3.4.7 Revision 115 3/29/11 B 3.4.8 Revision 115 3/29/11 B 3.4.9 Revision 115 3/29/11 B 3.4.10 Revision 102 8/17/09 B 3.4.11 Revision 115 3/29/11 B 3.4.12 Revision 115 3/29/11 B 3.4.13 Revision 126 5/1/13 B 3.4.14 Revision 115 3/29/11 B 3.4.15 Revision 115 3/29/11 B 3.4.16 Revision 121 8/5/09 B 3.4.17 Revision 115 3/29/11 B 3.4.18 Revision 86 6/25/07 B 3.5.1 Revision 115 3/29/11 B 3.5.2 Revision 116 8/18/11 B 3.5.3 Revision 57 4/29/04 B 3.5.4 Revision 122 10/25/12 B 3.5.5 Revision 115 3/29/11 B 3.6.1 Revision 53 2/17/04 B 3.6.2 Revision 115 3/29/11 B 3.6.3 Revision 115 3/29/11 B 3.6.4 Revision 115 3/29/11 B 3.6.5 Revision 115 3/29/11 B 3.6.6 Revision 122 10/25/12 B 3.6.7 Not Used - Revision 63 4/4/05 B 3.6.8 Revision 115 3/29/11 B 3.6.9 Revision 131 4/14/14 B 3.6.10 Revision 120 4/26/12 B 3.6.11 Revision 122 10/25/12 B 3.6.12 Revision 115 3/29/11 B 3.6.13 Revision 115 3/29/11 B 3.6.14 Revision 115 3/29/11 B 3.6.15 Revision 125 10/19/12 B 3.6.16 Revision 130 4/7/14 McGuire Units 1 and 2 Page 2 Revision 119
Page Number Amendment Revision Date B 3.7.1 Revision 129 10/24/13 B 3.7.2 Revision 105 2/22/10 B 3.7.3 Revision 102 8/17/09 B 3.7.4 Revision 115 3/29/11 B 3.7.5 Revision 115 3/29/11 B 3.7.6 Revision 127 8/2/13 B 3.7.7 Revision 115 3/29/11 B 3.7.8 Revision 128 10/2/13 B 3.7.9 Revision 120 4/26/12 B 3.7.10 Revision 115 3/29/11 B 3.7.11 Revision 115 3/29/11 B 3.7.12 Revision 115 3/29/11 B 3.7.13 Revision 115 3/29/11 B 3.7.14 Revision 115 3/29/11 B 3.7.15 Revision 66 6/30/05 B 3.7.16 Revision 115 3/29/11 B 3.8.1 Revision 115 3/29/11 B 3.8.2 Revision 92 1/28/08 B 3.8.3 Revision 123 9/29/12 B 3.8.4 Revision 115 3/29/11 B 3.8.5 Revision 41 7/29/03 B 3.8.6 Revision 115 3/29/11 B 3.8.7 Revision 115 3/29/11 B 3.8.8 Revision 115 3/29/11 B 3.8.9 Revision 115 3/29/11 B 3.8.10 Revision 115 3/29/11 B 3.9.1 Revision 115 3/29/11 B 3.9.2 Revision 115 3/29/11 B 3.9.3 Revision 115 3/29/11 B 3.9.4 Revision 115 3/29/11 B 3.9.5 Revision 115 3/29/11 B 3.9.6 Revision 115 3/29/11 B 3.9.7 Revision 115 3/29/11 McGuire Units I and 2 Page 3 Revision 119
Reactor Building B 3.6.16 B 3.6 CONTAINMENT SYSTEMS B 3.6.16 Reactor Building BASES BACKGROUND The reactor building is a concrete structure that surrounds the steel containment vessel. Between the containment vessel and the reactor building inner wall is an annular space that collects containment leakage that may occur following a loss of coolant accident (LOCA). This space also allows for periodic inspection of the outer surface of the steel containment vessel.
The Annulus Ventilation System (AVS) establishes a negative pressure in the annulus between the reactor building and the steel containment vessel under post accident conditions. Filters in the system then control the release of radioactive contaminants to the environment. The reactor building is required to be OPERABLE to ensure retention of containment leakage and proper operation of the AVS. To ensure the retention of containment leakage within the reactor building:
- a. The door in each access opening is closed except when the access opening is being used for normal transit entry and exit.
- b. The sealing mechanism associated with each penetration (e.g.,
welds, bellows, or O-rings) is OPERABLE.
APPLICABLE The design basis for reactor building OPERABILITY is a LOCA.
SAFETY ANALYSES Maintaining reactor building OPERABILITY ensures that the release of radioactive material from the containment atmosphere is restricted to those leakage paths and associated leakage rates assumed in the accident analyses.
The reactor building satisfies Criterion 3 of 10 CFR 50.36 (Ref. 1).
LCO Reactor building OPERABILITY must be maintained to ensure proper operation of the AVS and to limit radioactive leakage from the containment to those paths and leakage rates assumed in the accident analyses.
McGuire Units 1 and 2 B 3.6.16-1 Revision No. 130
Reactor Building B 3.6.16 BASES APPLICABILITY Maintaining reactor building OPERABILITY prevents leakage of radioactive material from the reactor building. Radioactive material may enter the reactor building from the containment following a LOCA.
Therefore, reactor building OPERABILITY is required in MODES 1, 2, 3, and 4 when a steam line break, LOCA, or rod ejection accident could release radioactive material to the containment atmosphere.
In MODES 5 and 6, the probability and consequences of these events are low due to the Reactor Coolant System temperature and pressure limitations in these MODES. Therefore, reactor building OPERABILITY is not required in MODE 5 or 6.
ACTIONS A.1 In the event reactor building OPERABILITY is not maintained, reactor building OPERABILITY must be restored within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Twenty-four hours is a reasonable Completion Time considering the limited leakage design of containment and the low probability of a Design Basis Accident occurring during this time period.
B.1 and B.2 If the reactor building cannot be restored to OPERABLE status within the required Completion Time, the plant must be brought to a MODE in which the LCO does not apply. To achieve this status, the plant must be brought to at least MODE 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and to MODE 5 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. The allowed Completion Times are reasonable, based on operating experience, to reach the required plant conditions from full power conditions in an orderly manner and without challenging plant systems.
SURVEILLANCE SR 3.6.16.1 REQUIREMENTS Maintaining reactor building OPERABILITY requires maintaining the door in each access opening closed, except when the access opening is being used for normal transit entry and exit. The Surveillance Frequency is based on operating experience, equipment reliability, and plant risk and is controlled under the Surveillance Frequency Control Program.
McGuire Units 1 and 2 B 3.6.16-2 Revision No. 130
Reactor Building B 3.6.16 BASES SURVEILLANCE REQUIREMENTS (continued)
SR 3.6.16.2 The ability of a AVS train to produce the required negative pressure within the required times provides assurance that the building is adequately sealed. The negative pressure prevents leakage from the building, since outside air will be drawn in by the low pressure. The negative pressure must be established within the time limit to ensure that no significant quantity of radioactive material leaks from the reactor building prior to developing the negative pressure.
The basis for the times and setpoints are provided in TS Bases 3.6.10, "Annulus Ventilation System (AVS)," Applicable Safety Analysis Section.
The Surveillance Frequency is based on operating experience, equipment reliability, and plant risk and is controlled under the Surveillance Frequency Control Program.
SR 3.6.16.3 This SR would give advance indication of gross deterioration of the concrete structural integrity of the reactor building. The Surveillance Frequency is based on operating experience, equipment reliability, and plant risk and is controlled under the Surveillance Frequency Control Program.
REFERENCES 1. 10 CFR 50.36, Technical Specifications, (c)(2)(ii).
McGuire Units 1 and 2 B 3.6.16-3 Revision No. 130
HMS B 3.6.9 B 3.6 CONTAINMENT SYSTEMS B 3.6.9 Hydrogen Mitigation System (HMS)
BASES BACKGROUND The HMS reduces the potential for breach of primary containment due to a hydrogen oxygen reaction in post accident environments. The HMS is required by 10 CFR 50.44, "Standards for Combustible Gas Control Systems in Light-Water-Cooled Reactors" (Ref. 1), and Appendix A, GDC 41, "Containment Atmosphere Cleanup" (Ref. 2), to reduce the hydrogen concentration in the primary containment following a degraded core accident. The HMS must be capable of handling an amount of hydrogen equivalent to that generated from a metal water reaction involving 75% of the fuel cladding surrounding the active fuel region (excluding the plenum volume).
10 CFR 50.44 (Ref. 1) requires units with ice condenser containments to install suitable hydrogen control systems that would accommodate an amount of hydrogen equivalent to that generated from the reaction of 75% of the fuel cladding with water. The HMS provides this required capability. This requirement was placed on ice condenser units because of their small containment volume and low design pressure (compared with pressurized water reactor dry containments). Calculations indicate that if hydrogen equivalent to that generated from the reaction of 75% of the fuel cladding with water were to collect in the primary containment, the resulting hydrogen concentration would be far above the lower flammability limit such that, if ignited from a random ignition source, the resulting hydrogen burn would seriously challenge the containment and safety systems in the containment.
The HMS is based on the concept of controlled ignition using thermal ignitors, designed to be capable of functioning in a post accident environment, seismically supported, and capable of actuation from the control room. A total of 70 ignitors are distributed throughout the various regions of containment in which hydrogen could be released or to which it could flow in significant quantities. The ignitors are arranged in two independent trains such that each containment region has at least two ignitors, one from each train, controlled and powered redundantly so that ignition would occur in each region even if one train failed to energize.
When the HMS is initiated, the ignitor elements are energized and heat up to a surface temperature >_1700 0 F. At this temperature, they ignite the hydrogen gas that is present in the airspace in the vicinity of the ignitor.
The HMS depends on the dispersed location of the ignitors so McGuire Units 1 and 2 B 3.6.9-1 Revision No. 131
HMS B 3.6.9 BASES BACKGROUND (continued) that local pockets of hydrogen at increased concentrations would burn before reaching a hydrogen concentration significantly higher than the lower flammability limit. Hydrogen ignition in the vicinity of the ignitors is assumed to occur when the local hydrogen concentration reaches 8.5 volume percent (v/o) and results in 100% of the hydrogen present being consumed.
APPLICABLE The HMS causes hydrogen in containment to burn in a controlled manner SAFETY ANALYSES as it accumulates following a degraded core accident (Ref. 3). Burning occurs at the lower flammability concentration, where the resulting temperatures and pressures are relatively benign. Without the system, hydrogen could build up to higher concentrations that could result in a violent reaction if ignited by a random ignition source after such a buildup.
The hydrogen ignitors are not included for mitigation of a Design Basis Accident (DBA) because an amount of hydrogen equivalent to that generated from the reaction of 75% of the fuel cladding with water is far in excess of the hydrogen calculated for the limiting DBA loss of coolant accident (LOCA). The hydrogen ignitors have been shown by probabilistic risk analysis to be a significant contributor to limiting the severity of accident sequences that are commonly found to dominate risk for units with ice condenser containments. As such, the hydrogen ignitors satisfy Criterion 4 of 10 CFR 50.36 (Ref. 4).
LCO Two HMS trains must be OPERABLE with power from two independent, safety related power supplies.
For this unit, an OPERABLE HMS train consists of 34 of 35 ignitors energized on the train.
Operation with at least one HMS train ensures that the hydrogen in containment can be burned in a controlled manner. Unavailability of both HMS trains could lead to hydrogen buildup to higher concentrations, which could result in a violent reaction if ignited. The reaction could take place fast enough to lead to high temperatures and overpressurization of containment and, as a result, breach containment or cause containment leakage rates above those assumed in the safety analyses. Damage to safety related equipment located in containment could also occur.
Revision No. 131 McGuire Units McGuire and 22 Units 11 and B 3.6.9-2 B 3.6.9-2 Revision No. 131
HMS B 3.6.9 BASES APPLICABILITY Requiring OPERABILITY in MODES 1 and 2 for the HMS ensures its immediate availability after safety injection and scram actuated on a LOCA initiation. In the post accident environment, the two HMS subsystems are required to control the hydrogen concentration within containment to near its flammability limit of 4.0 v/o assuming a worst case single failure. This prevents overpressurization of containment and damage to safety related equipment and instruments located within containment.
In MODES 3 and 4, both the hydrogen production rate and the total hydrogen production after a LOCA would be tignificantly less than that calculated for the DBA LOCA. Also, because of the limited time in these MODES, the probability of an accident requiring the HMS is low.
Therefore, the HMS is not required in MODES 3 and 4.
In MODES 5 and 6, the probability and consequences of a LOCA are reduced due to the pressure and temperature limitations of these MODES. Therefore, the HMS is not required to be OPERABLE in MODES 5 and 6.
ACTIONS A.1 and A.2 With one HMS train inoperable, the inoperable train must be restored to OPERABLE status within 7 days or the OPERABLE train must be verified OPERABLE frequently by performance of SR 3.6.9.1. The 7 day Completion Time is based on the low probability of the occurrence of a degraded core event that would generate hydrogen in amounts equivalent to a metal water reaction of 75% of the core cladding, the length of time after the event that operator action would be required to prevent hydrogen accumulation from exceeding this limit, and the low probability of failure of the OPERABLE HMS train. Alternative Required Action A.2, by frequent surveillances, provides assurance that the OPERABLE train continues to be OPERABLE.
B. 1 Condition B is one containment region with no OPERABLE hydrogen ignitor. Thus, while in Condition B, or in Conditions A and B simultaneously, there would always be ignition capability in the adjacent containment regions that would provide redundant capability by flame propagation to the region with no OPERABLE ignitors.
Required Action B.1 calls for the restoration of one hydrogen ignitor in each region to OPERABLE status within 7 days. The 7 day Completion Time is based on the same reasons given under Required Action A.1.
McGuire Units 1 and 2 B 3.6.9-3 Revision No. 131
HMS B 3.6.9 BASES ACTIONS (continued)
C.1 The unit must be placed in a MODE in which the LCO does not apply if the HMS subsystem(s) cannot be restored to OPERABLE status within the associated Completion Time. This is done by placing the unit in at least MODE 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. The allowed Completion Time of 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> is reasonable, based on operating experience, to reach MODE 3 from full power conditions in an orderly manner and without challenging plant systems.
SURVEILLANCE SR 3.6.9.1 REQUIREMENTS This SR confirms that _>34 of 35 hydrogen ignitors can be successfully energized in each train. The ignitors are simple resistance elements.
Therefore, energizing provides assurance of OPERABILITY. The allowance of one inoperable hydrogen ignitor is acceptable because, although one inoperable hydrogen ignitor in a region would compromise redundancy in that region, the containment regions are interconnected so that ignition in one region would cause burning to progress to the others (i.e., there is overlap in each hydrogen ignitor's effectiveness between regions). The Surveillance Frequency is based on operating experience, equipment reliability, and plant risk and is controlled under the Surveillance Frequency Control Program.
SR 3.6.9.2 This SR confirms that the two inoperable hydrogen ignitors allowed by SR 3.6.9.1 (i.e., one in each train) are not in the same containment region. The Surveillance Frequency is based on operating experience, equipment reliability, and plant risk and is controlled under the Surveillance Frequency Control Program.
SR 3.6.9.3 A more detailed functional test is performed to verify system OPERABILITY. Each ignitor is visually examined to ensure that it is clean and that the electrical circuitry is energized. All ignitors, including normally inaccessible ignitors, are visually checked for a glow to verify that they are energized. Additionally, the surface temperature of each ignitor is measured to be _>1700°F to demonstrate that a temperature sufficient for ignition is achieved. The Surveillance Frequency is based on operating experience, equipment reliability, and plant risk and is controlled under the Surveillance Frequency Control Program.
McGuire Units 1 and 2 B 3.6.9-4 Revision No. 131
HMS B 3.6.9 BASES REFERENCES 1. 10 CFR 50.44.
- 2. 10 CFR 50, Appendix A, GDC 41.
- 3. UFSAR, Section 6.2.
- 4. 10 CFR 50.36, Technical Specifications, (c)(2)(ii).
McGuire Units I and 2 B 3.6.9-5 Revision No. 131