Letter Sequence Request |
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Results
Other: L-MT-05-115, Response to Two Requests for Additional Information Regarding the Monticello Nuclear Generating Plant License Renewal Application, L-MT-06-015, Confirmatory Items Response Regarding the Monticello Nuclear Generating Plant License Renewal Application, L-MT-06-018, License Renewal Application Annual Update, L-MT-06-049, (Mngp), Comments Regarding the Safety Evaluation Report for MNGP License Renewal Application, L-MT-06-060, License Renewal Application Update, ML051580005, ML051600008, ML051600081, ML060340200, ML070450211
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MONTHYEARL-MT-05-014, Transmittal of Monticello Nuclear Generating Plant Application for Renewed Operating License2005-03-16016 March 2005 Transmittal of Monticello Nuclear Generating Plant Application for Renewed Operating License Project stage: Request ML0513802172005-05-11011 May 2005 Presentation Slides Used at Meeting on May 11, 2005, Between the NRC and NMC to Discuss Monticello LRA Project stage: Meeting ML0516000082005-06-0202 June 2005 Audit & Review Plan for Plant Aging Management Reviews & Programs for Monticello Nuclear Generating Plant Project stage: Other ML0515800052005-06-0202 June 2005 Audit and Review Plan for Plant Aging Management Reviews and Programs for the Monticello Generating Plant Project stage: Other ML0516000812005-06-0909 June 2005 Memo Issuing Audit and Review Plan for Plant Aging Management Reviews and Programs for the Monticello Nuclear Generating Plant Project stage: Other L-MT-05-093, License Amendment Request - Full Scope Application of an Alternative Source Term2005-09-15015 September 2005 License Amendment Request - Full Scope Application of an Alternative Source Term Project stage: Request L-MT-05-115, Response to Two Requests for Additional Information Regarding the Monticello Nuclear Generating Plant License Renewal Application2005-11-22022 November 2005 Response to Two Requests for Additional Information Regarding the Monticello Nuclear Generating Plant License Renewal Application Project stage: Other ML0603402002006-01-30030 January 2006 Summary of a Telephone Conference Call Held on 01/12/ 2006, Between the U.S. Nuclear Regulatory Commission and Nuclear Management Company, LLC, Concerning Information Pertaining to the Monticello Nuclear Generating Plant License Renewal App Project stage: Other L-MT-06-014, Supplement to Responses to Requests for Additional Information Regarding the Monticello Nuclear Generating Plant License Renewal Application2006-02-27027 February 2006 Supplement to Responses to Requests for Additional Information Regarding the Monticello Nuclear Generating Plant License Renewal Application Project stage: Response to RAI L-MT-06-015, Confirmatory Items Response Regarding the Monticello Nuclear Generating Plant License Renewal Application2006-02-28028 February 2006 Confirmatory Items Response Regarding the Monticello Nuclear Generating Plant License Renewal Application Project stage: Other L-MT-06-018, License Renewal Application Annual Update2006-03-15015 March 2006 License Renewal Application Annual Update Project stage: Other L-MT-06-019, Supplemental Information and Response to Requests for Additional Information Regarding Monticello Nuclear Generating Plant License Renewal Application2006-03-31031 March 2006 Supplemental Information and Response to Requests for Additional Information Regarding Monticello Nuclear Generating Plant License Renewal Application Project stage: Response to RAI L-MT-06-029, Supplemental Information Regarding Monticello Nuclear Generating Plant License Renewal Application2006-04-10010 April 2006 Supplemental Information Regarding Monticello Nuclear Generating Plant License Renewal Application Project stage: Supplement L-MT-06-037, Comments Regarding the Draft Plant-Specify Supplement 26 to the Generic Environmental Impact Statement for Plant License Renewal Application2006-04-26026 April 2006 Comments Regarding the Draft Plant-Specify Supplement 26 to the Generic Environmental Impact Statement for Plant License Renewal Application L-MT-06-049, (Mngp), Comments Regarding the Safety Evaluation Report for MNGP License Renewal Application2006-06-15015 June 2006 (Mngp), Comments Regarding the Safety Evaluation Report for MNGP License Renewal Application Project stage: Other ML0617805322006-06-23023 June 2006 Supplemental Information Regarding the Monticello Nuclear Generating Plant License Renewal Application Project stage: Supplement L-MT-06-060, License Renewal Application Update2006-08-18018 August 2006 License Renewal Application Update Project stage: Other ML0704502112007-02-23023 February 2007 Letter Correcting Errors in Renewed Facility Operating License Project stage: Other 2006-02-28
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Category:Letter type:L
MONTHYEARL-MT-23-054, Subsequent License Renewal Application Supplement 82024-01-11011 January 2024 Subsequent License Renewal Application Supplement 8 L-MT-23-047, License Amendment Request: Revision to the MNGP Pressure Temperature Limits Report to Change the Neutron Fluence Methodology and Incorporate New Surveillance Capsule Data2023-12-29029 December 2023 License Amendment Request: Revision to the MNGP Pressure Temperature Limits Report to Change the Neutron Fluence Methodology and Incorporate New Surveillance Capsule Data L-MT-23-056, Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 1 Part 22023-12-18018 December 2023 Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 1 Part 2 L-MT-23-042, 2023 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.462023-12-11011 December 2023 2023 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46 L-MT-23-052, Subsequent License Renewal Application Supplement 72023-11-30030 November 2023 Subsequent License Renewal Application Supplement 7 L-MT-23-051, Update to the Technical Specification Bases2023-11-28028 November 2023 Update to the Technical Specification Bases L-MT-23-049, Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 12023-11-21021 November 2023 Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 1 L-MT-23-043, 10 CFR 50.55a(z)(1) Request Regarding OMN-17, Revision 1. VR-092023-11-13013 November 2023 10 CFR 50.55a(z)(1) Request Regarding OMN-17, Revision 1. VR-09 L-MT-23-038, License Amendment Request to Revise Monticello Technical Specification Surveillance Requirement 3.8.6.62023-11-10010 November 2023 License Amendment Request to Revise Monticello Technical Specification Surveillance Requirement 3.8.6.6 L-MT-23-046, Subsequent License Renewal Application Response to Request for Additional Information Round 2 - Set 12023-11-0909 November 2023 Subsequent License Renewal Application Response to Request for Additional Information Round 2 - Set 1 L-MT-23-041, Subsequent License Renewal Application Response to Request for Confirmation of Information Set 22023-10-0303 October 2023 Subsequent License Renewal Application Response to Request for Confirmation of Information Set 2 L-MT-23-037, Subsequent License Renewal Application Response to Request for Additional Information Set 32023-09-22022 September 2023 Subsequent License Renewal Application Response to Request for Additional Information Set 3 L-MT-23-036, Subsequent License Renewal Application Response to Request for Additional Information Set 2 and Supplement 62023-09-0505 September 2023 Subsequent License Renewal Application Response to Request for Additional Information Set 2 and Supplement 6 L-MT-23-035, Subsequent License Renewal Application Supplement 52023-08-28028 August 2023 Subsequent License Renewal Application Supplement 5 L-MT-23-034, Subsequent License Renewal Application Response to Request for Additional Information Set 12023-08-15015 August 2023 Subsequent License Renewal Application Response to Request for Additional Information Set 1 L-MT-23-028, 2023 Refueling Outage 90-Day Inservice Inspection (ISI) Summary Report2023-07-31031 July 2023 2023 Refueling Outage 90-Day Inservice Inspection (ISI) Summary Report L-MT-23-032, 10 CFR 50.55a(z)(2) Request Regarding MO-2397, VR-112023-07-31031 July 2023 10 CFR 50.55a(z)(2) Request Regarding MO-2397, VR-11 L-MT-23-031, Subsequent License Renewal Application Supplement 4 and Responses to Request for Confirmation of Information - Set 12023-07-18018 July 2023 Subsequent License Renewal Application Supplement 4 and Responses to Request for Confirmation of Information - Set 1 L-MT-23-030, Subsequent License Renewal Application Supplement 32023-07-0404 July 2023 Subsequent License Renewal Application Supplement 3 L-MT-23-025, Subsequent License Renewal Application Supplement 22023-06-26026 June 2023 Subsequent License Renewal Application Supplement 2 L-MT-23-019, Submittal of 2022 Annual Radiological Environmental Operating Report2023-05-10010 May 2023 Submittal of 2022 Annual Radiological Environmental Operating Report L-MT-23-020, Submittal of 2022 Annual Radioactive Effluent Release Report2023-05-10010 May 2023 Submittal of 2022 Annual Radioactive Effluent Release Report L-MT-23-021, Core Operating Limits Report (COLR) for the Monticello Nuclear Generating Plant for Cycle 322023-05-0202 May 2023 Core Operating Limits Report (COLR) for the Monticello Nuclear Generating Plant for Cycle 32 L-MT-23-017, 2022 Annual Report of Individual Monitoring for the Monticello Nuclear Generating Plant (MNGP)2023-04-18018 April 2023 2022 Annual Report of Individual Monitoring for the Monticello Nuclear Generating Plant (MNGP) L-MT-23-010, Subsequent License Renewal Application Supplement 12023-04-0303 April 2023 Subsequent License Renewal Application Supplement 1 L-MT-23-013, Core Operating Limits Report (COLR) for Cycle 31, Revision 32023-03-28028 March 2023 Core Operating Limits Report (COLR) for Cycle 31, Revision 3 L-MT-23-012, Core Operating Limits Report (COLR) for Monticello Nuclear Generating Plant Cycle 31, Revision 22023-03-17017 March 2023 Core Operating Limits Report (COLR) for Monticello Nuclear Generating Plant Cycle 31, Revision 2 L-MT-23-008, 10CFR50.55a Request to Use Later Edition of ASME Section XI for ISI Code of Record (RR-003)2023-02-0707 February 2023 10CFR50.55a Request to Use Later Edition of ASME Section XI for ISI Code of Record (RR-003) L-MT-23-004, CFR 50.55a Request RR-001, Request to Use a Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI for the Monticello Third Interval Containment Inservice Inspection Program2023-01-23023 January 2023 CFR 50.55a Request RR-001, Request to Use a Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI for the Monticello Third Interval Containment Inservice Inspection Program L-MT-23-005, Response to the NRC Request for Additional Information Regarding the 50.55a Request Pr 08, HPCI Pump Quarterly Testing (EPID Number L-2022-LLR-0088)2023-01-0606 January 2023 Response to the NRC Request for Additional Information Regarding the 50.55a Request Pr 08, HPCI Pump Quarterly Testing (EPID Number L-2022-LLR-0088) L-MT-22-049, Industry Groundwater Protection Initiative Special Report2022-12-15015 December 2022 Industry Groundwater Protection Initiative Special Report L-MT-22-052, L-MT-22-052 Monticello Nuclear Generating Plant 10 CFR 50.55a Request No. Pr 08, Request for HPCI Pump Quarterly Alternative2022-12-15015 December 2022 L-MT-22-052 Monticello Nuclear Generating Plant 10 CFR 50.55a Request No. Pr 08, Request for HPCI Pump Quarterly Alternative L-MT-22-046, 2022 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.462022-12-13013 December 2022 2022 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46 L-MT-22-048, Update to the Monticello Technical Specification Bases2022-11-28028 November 2022 Update to the Monticello Technical Specification Bases L-MT-22-047, Withdrawal of Request for Relief from ASME OM Code for the Sixth Inservice Testing Interval2022-11-10010 November 2022 Withdrawal of Request for Relief from ASME OM Code for the Sixth Inservice Testing Interval L-MT-22-045, Letter Submitting Post-Exam Package2022-11-0404 November 2022 Letter Submitting Post-Exam Package L-MT-22-030, Sixth Interval Inservice Testing (1ST) Plan2022-09-0606 September 2022 Sixth Interval Inservice Testing (1ST) Plan L-MT-22-037, Supplement to 10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval, Alternative VR-10, Excess Flow Check Valve Testing Frequency2022-08-29029 August 2022 Supplement to 10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval, Alternative VR-10, Excess Flow Check Valve Testing Frequency L-MT-22-007, Response to Request for Additional Information for the Monticello Nuclear Generating Plant Alternative Request VR-08 (EPID: L-MT-22-007)2022-07-22022 July 2022 Response to Request for Additional Information for the Monticello Nuclear Generating Plant Alternative Request VR-08 (EPID: L-MT-22-007) L-MT-22-026, Changes to the Emergency Plan2022-07-19019 July 2022 Changes to the Emergency Plan L-MT-22-024, Response to a Request for Additional Information for the Monticello Nuclear Generating Plant Related to the Amendment to Adopt Advanced Framatome Methodologies2022-06-0606 June 2022 Response to a Request for Additional Information for the Monticello Nuclear Generating Plant Related to the Amendment to Adopt Advanced Framatome Methodologies L-MT-22-022, Response to a Request for Additional Information: Monticello Alternative VR-10, Excess Flow Check Valve Testing Frequency2022-05-25025 May 2022 Response to a Request for Additional Information: Monticello Alternative VR-10, Excess Flow Check Valve Testing Frequency L-MT-22-017, 2021 Annual Radiological Environmental Operating Report2022-05-11011 May 2022 2021 Annual Radiological Environmental Operating Report L-MT-22-018, 2021 Annual Radioactive Effluent Release Report2022-05-11011 May 2022 2021 Annual Radioactive Effluent Release Report L-MT-22-016, 2021 Annual Report of Individual Monitoring2022-04-28028 April 2022 2021 Annual Report of Individual Monitoring L-MT-22-019, Withdrawal of Requests for Relief from ASME OM Code for the Sixth Inservice Testing Interval2022-04-18018 April 2022 Withdrawal of Requests for Relief from ASME OM Code for the Sixth Inservice Testing Interval L-MT-22-010, License Amendment Request to Revise Technical Specification 3.6.1.8 Residual Heat Removal (RHR) Drywell Spray Header and Nozzle Surveillance Frequency2022-03-18018 March 2022 License Amendment Request to Revise Technical Specification 3.6.1.8 Residual Heat Removal (RHR) Drywell Spray Header and Nozzle Surveillance Frequency L-MT-22-012, Special Report for the Bypass of the Offgas Treatment Storage System2022-03-15015 March 2022 Special Report for the Bypass of the Offgas Treatment Storage System L-MT-22-008, 10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval Alternative Related to Excess Flow Check Valve Testing Frequency (L-MT-22-008)2022-03-0707 March 2022 10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval Alternative Related to Excess Flow Check Valve Testing Frequency (L-MT-22-008) L-MT-22-006, 10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval OMN-26 (L-MT-22-006)2022-02-18018 February 2022 10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval OMN-26 (L-MT-22-006) 2024-01-11
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARL-MT-23-054, Subsequent License Renewal Application Supplement 82024-01-11011 January 2024 Subsequent License Renewal Application Supplement 8 L-MT-23-047, License Amendment Request: Revision to the MNGP Pressure Temperature Limits Report to Change the Neutron Fluence Methodology and Incorporate New Surveillance Capsule Data2023-12-29029 December 2023 License Amendment Request: Revision to the MNGP Pressure Temperature Limits Report to Change the Neutron Fluence Methodology and Incorporate New Surveillance Capsule Data L-MT-23-038, License Amendment Request to Revise Monticello Technical Specification Surveillance Requirement 3.8.6.62023-11-10010 November 2023 License Amendment Request to Revise Monticello Technical Specification Surveillance Requirement 3.8.6.6 L-MT-23-035, Subsequent License Renewal Application Supplement 52023-08-28028 August 2023 Subsequent License Renewal Application Supplement 5 L-MT-23-031, Subsequent License Renewal Application Supplement 4 and Responses to Request for Confirmation of Information - Set 12023-07-18018 July 2023 Subsequent License Renewal Application Supplement 4 and Responses to Request for Confirmation of Information - Set 1 L-MT-23-025, Subsequent License Renewal Application Supplement 22023-06-26026 June 2023 Subsequent License Renewal Application Supplement 2 L-MT-23-010, Subsequent License Renewal Application Supplement 12023-04-0303 April 2023 Subsequent License Renewal Application Supplement 1 ML23009A3542023-01-0909 January 2023 Subsequent License Renewal Application Sections 1 - 4 and Appendices a - D L-MT-22-010, License Amendment Request to Revise Technical Specification 3.6.1.8 Residual Heat Removal (RHR) Drywell Spray Header and Nozzle Surveillance Frequency2022-03-18018 March 2022 License Amendment Request to Revise Technical Specification 3.6.1.8 Residual Heat Removal (RHR) Drywell Spray Header and Nozzle Surveillance Frequency L-MT-21-072, License Amendment Request: Revise MNGP Technical Specifications to Support a Ten-Year Inspection of the Diesel Generator Fuel Oil Storage Tank2021-12-13013 December 2021 License Amendment Request: Revise MNGP Technical Specifications to Support a Ten-Year Inspection of the Diesel Generator Fuel Oil Storage Tank L-MT-21-067, Update to the Monticello Technical Specification Bases2021-11-29029 November 2021 Update to the Monticello Technical Specification Bases ML21320A2262021-11-15015 November 2021 License Amendment Request: Standard Emergency Plan and Consolidated Emergency Operations Facility for the Monticello Nuclear Generating Plant and the Prairie Island Nuclear Generating Plant L-MT-21-043, Supplement to License Amendment Request: Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2021-06-30030 June 2021 Supplement to License Amendment Request: Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b L-MT-20-023, License Amendment Request: Application to Revise Technical Specifications to Adopt TSTF-564, Safety Limit MCPR2020-11-0303 November 2020 License Amendment Request: Application to Revise Technical Specifications to Adopt TSTF-564, Safety Limit MCPR L-MT-20-018, License Amendment Request: Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements2020-09-22022 September 2020 License Amendment Request: Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements L-MT-20-003, License Amendment Request: Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times-RITSTF Initiative 4b2020-03-30030 March 2020 License Amendment Request: Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times-RITSTF Initiative 4b ML20058F9432020-02-27027 February 2020 and Prairie Island Nuclear Generating Plant, Units 1 and 2 - License Amendment Request: Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules Revision 4 L-MT-18-073, Supplement to License Amendment Request: Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee...2018-11-20020 November 2018 Supplement to License Amendment Request: Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee... L-MT-18-009, License Amendment Request: Revise Limiting Condition for Operation (LCO) of Specification 3.5.1, Emergency Core Cooling System - Operating, to Remove the LCO Note2018-11-12012 November 2018 License Amendment Request: Revise Limiting Condition for Operation (LCO) of Specification 3.5.1, Emergency Core Cooling System - Operating, to Remove the LCO Note L-MT-18-060, License Amendment Request: Revise the Safety Limit Minimum Critical Power Ratio in Reactor Core Safety Limit 2.1.12018-11-12012 November 2018 License Amendment Request: Revise the Safety Limit Minimum Critical Power Ratio in Reactor Core Safety Limit 2.1.1 L-MT-18-051, Supplement to License Amendment Request to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control,2018-09-11011 September 2018 Supplement to License Amendment Request to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, L-MT-18-006, Application to Revise Technical Specifications to Adopt TSTF-551, Revision 3, Revise Secondary Containment Surveillance Requirements2018-07-0303 July 2018 Application to Revise Technical Specifications to Adopt TSTF-551, Revision 3, Revise Secondary Containment Surveillance Requirements L-MT-18-020, Supplement to License Amendment Request: Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Control2018-04-24024 April 2018 Supplement to License Amendment Request: Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Control L-MT-18-010, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2018-03-28028 March 2018 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors L-MT-17-083, License Amendment Request: Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program2017-12-19019 December 2017 License Amendment Request: Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program L-MT-17-058, Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control2017-10-20020 October 2017 Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control ML17095A1142017-03-31031 March 2017 License Amendment Request to Revise Emergency Action Level Scheme: Attachment 4, Supporting Calculations for EAL Thresholds, Part 2 of 5 ML17095A1202017-03-31031 March 2017 License Amendment Request to Revise Emergency Action Level Scheme: Attachment 4, Supporting Calculations for EAL Thresholds, Part 5 of 5 ML17090A2012017-03-31031 March 2017 License Amendment Request to Revise Technical Specification for Plant/Unit Staff Qualifications Education and Experience Eligibility Requirements for Licensed Operators ML17095A1152017-03-31031 March 2017 License Amendment Request to Revise Emergency Action Level Scheme: Attachment 4, Supporting Calculations for EAL Thresholds, Part 3 of 5 ML17095A1132017-03-31031 March 2017 License Amendment Request to Revise Emergency Action Level Scheme: Attachment 4, Supporting Calculations for EAL Thresholds, Part 1 of 5 ML17095A1182017-03-31031 March 2017 License Amendment Request to Revise Emergency Action Level Scheme: Attachment 4, Supporting Calculations for EAL Thresholds, Part 4 of 5 ML17095A1122017-03-31031 March 2017 License Amendment Request to Revise Emergency Action Level Scheme: Attach. 1, EAL Comparison Matrix Document (Deviations & Differences) and Attachments 2 & 3, Red-Line & Clean Versions of EAL Technical Bases Document L-MT-16-031, 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, and to Request an Alternative to the ASME Code2016-07-28028 July 2016 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, and to Request an Alternative to the ASME Code L-MT-16-014, License Amendment Request: Revise Battery Charger Surveillance Requirement 3.8.4.22016-04-0404 April 2016 License Amendment Request: Revise Battery Charger Surveillance Requirement 3.8.4.2 ML16047A2722016-02-10010 February 2016 License Amendment Request: Revise Technical Specification 5.5.11 to Provide a Permanent Extension of the Integrated Leakage Rate (Type a) Test Frequency from Ten to Fifteen Years L-MT-15-032, License Amendment Request to Revise Technical Specification Surveillance Requirement 3.5.1.3.b to Correct the Alternate Nitrogen System Pressure2015-09-0202 September 2015 License Amendment Request to Revise Technical Specification Surveillance Requirement 3.5.1.3.b to Correct the Alternate Nitrogen System Pressure L-MT-15-048, License Amendment Request: Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process2015-07-15015 July 2015 License Amendment Request: Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process L-MT-14-043, License Amendment Request for Fuel Storage Changes Supplement to Proposed Spent Fuel Pool Boral Monitoring Program Technical Specification2014-05-30030 May 2014 License Amendment Request for Fuel Storage Changes Supplement to Proposed Spent Fuel Pool Boral Monitoring Program Technical Specification ML14126A7272014-05-0505 May 2014 Supplement to License Amendment Request (LAR) for Cyber Security Plan Implementation Date Extension L-MT-14-009, License Amendment Request: Revision to Required Actions for Technical Specification 3.5.1, Emergency Core Cooling System (ECCS)2014-04-0404 April 2014 License Amendment Request: Revision to Required Actions for Technical Specification 3.5.1, Emergency Core Cooling System (ECCS) ML14072A3902014-03-13013 March 2014 License Amendment Request for Fuel Storage Changes, Supplement to Propose a Spent Fuel Pool Boral Monitoring Program Technical Specification ML13333B6742013-11-27027 November 2013 License Amendment Request (LAR) for Northern States Power Company, Minnesota (NSPM) Cyber Security Plan Implementation Date Extension L-MT-13-081, Maximum Extended Load Line Limit Analysis Plus License Amendment Request - Request for Additional Information Responses2013-08-14014 August 2013 Maximum Extended Load Line Limit Analysis Plus License Amendment Request - Request for Additional Information Responses L-MT-13-055, License Amendment Request for Transition to Areva Atrium 10XM Fuel and Areva Safety Analysis Methodology2013-07-15015 July 2013 License Amendment Request for Transition to Areva Atrium 10XM Fuel and Areva Safety Analysis Methodology L-MT-13-046, License Amendment Request for Fuel Storage Changes, Supplement to Respond to NRC Staff Requests for Additional Information2013-05-16016 May 2013 License Amendment Request for Fuel Storage Changes, Supplement to Respond to NRC Staff Requests for Additional Information L-MT-13-030, License Amendment Request: Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-535, Revision 0, Revise Shutdown Margin Definition to Address Advanced Fuel Designs2013-04-19019 April 2013 License Amendment Request: Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-535, Revision 0, Revise Shutdown Margin Definition to Address Advanced Fuel Designs L-MT-13-010, License Amendment Request: Reduce the Reactor Steam Dome Pressure Specified in the Reactor Core Safety Limits2013-03-11011 March 2013 License Amendment Request: Reduce the Reactor Steam Dome Pressure Specified in the Reactor Core Safety Limits L-MT-12-102, License Amendment Request: Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-522, Revision 0, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month.2013-01-0404 January 2013 License Amendment Request: Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-522, Revision 0, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month. L-MT-12-078, License Amendment Request: Modification to the MNGP Emergency Plan Concerning a Revision to the Emergency Action Level Setpoint for the Turbine Building Normal Waste Sump Monitor2012-12-21021 December 2012 License Amendment Request: Modification to the MNGP Emergency Plan Concerning a Revision to the Emergency Action Level Setpoint for the Turbine Building Normal Waste Sump Monitor 2024-01-11
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NM C Committed to Nuclear ExceIl Monticello Nuclear Generating Plant encOperated by Nuclear Management Company, LLC March 16, 2005 L-MT-05-014 10 CFR Part 54 US Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Monticello Nuclear Generating Plant Docket 50-263 License No. DPR-22 Application for Renewed Operating License Pursuant to U. S. Nuclear Regulatory Commission (NRC) regulations 10 CFR Parts 50, 51, and 54, Nuclear Management Company, LLC (NMC) hereby applies for renewal of the Operating License for the Monticello Nuclear Generating Plant (MNGP).
The current operating license for the Monticello plant expires at midnight, September 8, 2010. NMC requests that the MNGP Operating License be extended for 20 years beyond the current expiration date to midnight, September 8, 2030.
The enclosed 'Application for Renewed Operating License, March 2005" is submitted in accordance with the applicable requirements of 10 CFR Part 54, Sections 54.17, 54.19, 54.21, 54.22, and 54.23. This application meets the timeliness requirements of 10 CFR 2.109(b) and 10 CFR 54.17(c) and provides the administrative, technical, and environmental information sufficient to support the NRC findings required by 10 CFR 54.29.
Inaccordance with the requirements of 10 CFR 54.21, measures are described in this application which provide assurance that the effects of aging will be adequately managed, consistent with the current licensing basis, for the requested period of extended operation. In some cases, new aging management programs or enhancements to existing programs are described.
During the performance of the environmental review, no new and significant information was identified that would either invalidate NRC Category 1 findings in NUREG-1437 or identify any new issues requiring evaluation. A review of the applicable Category 2 issues determined that the impacts of MNGP license renewal will be small.
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Document Control Desk Page 2 Changes to the current licensing basis made subsequent to this application, and which have a material effect on the content of this application, will be identified in amendments to this document in accordance with 10 CFR 54.21 (b). Amendments will be submitted annually while the application is under NRC review, and at least three months prior to the scheduled completion of NRC review.
This application is being submitted in paper copy and electronic form following the guidance contained in the NRC Final Rule on Electronic Maintenance and Submission of Information (68 FR 58792). Enclosure 1 is a compact disc (CD) containing the entire License Renewal Application, including the Environmental Report, and a copy of this signed cover letter in Adobe PDF format. is a paper copy of the entire License Renewal Application, including the Environmental Report.
Summary of Commitments The commitments listed in Enclosure 3, "Compilation of Commitments Related to License Renewal Aging Management for the Monticello Nuclear Generating Plant,"
summarize those actions, new programs, and program enhancements committed to by NMC.
I declare under penalty of perjury that the foregoing is true and correct. Executed on Thomas J. Palmisano Site Vice President, Monticello Nuclear Generating Plant Nuclear Management Company, LLC
Document Control Desk Page 3 Enclosures (3)
- 1. CD titled, "Docket Copy, License Renewal Application, March 2005,"
including the scanned cover letter, complete MNGP application, and Environmental Report. Three files in Adobe PDF format are provided on the CD:
- 001_MNGPLRAtransmittalletter.pdf
- 003_MNGPLRA env report.pdf
- 2. One paper copy "Application for Renewed Operating License, March 2005," including the Environmental Report.
- 3. Compilation of Commitments Related to License Renewal Aging Management for the Monticello Nuclear Generating Plant.
cc (w/Enclosures I & 3):
Mayor, City of Monticello, Minnesota Minnesota Department of Commerce Project Manager Monticello, USNRC License Renewal Project Manager Monticello, USNRC Administrator, Region ll, USNRC Sr. Resident Inspector Monticello, USNRC
ENCLOSURE 3 COMPILATION OF COMMITMENTS RELATED TO LICENSE RENEWAL AGING MANAGEMENT FOR THE MONTICELLO NUCLEAR GENERATING PLANT The following table summarizes those actions committed to by Nuclear Management Company, LLC in this document.
Commitment Source I +
Each year, following the submittal of the MNGP License Renewal Application and at least three months before the scheduled completion of the NRC review, NMC will submit amendments to the MNGP application pursuant to 10 CFR 54.21 (b).
- 1. These revisions will identify any changes to the LRA Section 1.4 current licensing basis that materially affect the contents of the License Renewal Application, including the USAR supplements and any other aspects of the application.
1 4-In accordance with the guidance of Appendix A.3.2.1.2 of NUREG-1800, Appendix B of the latest issued supplement to NUREG-0933 will be reviewed for new GSIs designated as USI-, LRA Section
- 2. HIGH-, or MEDIUM- priority. Any identified that involve TLAAs or aging effects for structures and 3.0.7 components subject to an aging management review will be included in the annual update of the LRA.
Page 1 of 13
Commitment Source Inspection of the steam dryer is to be accomplished using the guidelines in the LRA Table approved BWRVIP topical report(s) for steam 3.1.2-3, Note
- 3. dryer inspection. Inthe event a new steam dryer 136 is installed, NMC will reevaluate the inspection requirements.
The interior of the Diesel Fire Pump House masonry block walls is covered with insulation.
The Structures Monitoring Program will require 3.5.2-8, Note
- 4. that the interior surfaces of the walls will be 51.
examined if exterior wall surfaces show evidence 516 of significant aging effects.
The procedures and training used to limit reactor pressure vessel cold over-pressure events will be the same as those approved by the NRC when MNGP requested approval of the BWRVIP-05 LRA Section
- 5. technical alternative for the term of the current 4.2.6 operating license. A request for extension for the 60-year extended operating period will be submitted to the NRC prior to the period of extended operation.
MNGP site-specific administrative work instructions will be applicable to both safety and non-safety related systems, structures and LRA Section
- 6. components that are subject to an aging B13.3 management review consistent with the current licensing basis during the period of extended operation.
Page 2 of 13
Commitment Source Site documents that implement aging management activities for license renewal will be enhanced to ensure that an AR is prepared in LRA Section
- 7. accordance with plant procedures whenever non- B1.3 conforming conditions are found (i.e., the acceptance criteria is not met).
Revisions will be made to procedures and instructions that implement or administer aging LRA Section
- 8. management programs and/or activities for the B1.3 purpose of managing the associated aging effects for the duration of extended operation.
The MNGP ASME Section Xl, Subsection IWF Program will be enhanced to provide inspections LRA Section
- 9. of Class MC components supports consistent B2.1.3 with NUREG-1801, Chapter III, Section B1.3.
The guidance for performing visual bolting inspections contained in EPRI TR-104213, Bolted Joint Maintenance & Application Guide, and the Good Bolting Practices Handbook (EPRI NP-5067 Volumes I and 2) will be included in the LRA Section
- 10. Bus Duct Inspection Program, Inspection of B2.1.4 Overhead Heavy Load and Light Load (Related to Refueling) Handling Systems Program, Structures Monitoring Program and the System Condition Monitoring Program.
Page 3 of 13
Commitment Source The Buried Piping and Tanks Inspection Program will be updated implementing procedures to LRA Section
- 11. include inspections of buried components when B2.1.5 they are uncovered.
The Diesel Fuel Oil Storage Tank, T-44, internal inspection will be added to the list of scheduled LRA Section
- 12. inspections in the Buried Piping and Tanks B2.1.5 Inspection Program.
The Buried Piping and Tanks Inspection Program will be revised to include a provision that if LRA Section
- 13. evaluations of pipe wall thickness show a B2.eto susceptibility to corrosion, further evaluation as to B2.1.5 the extent of susceptibility will be performed.
The Buried Piping and Tanks Inspection Program LRA Section
- 14. will be revised to specify a 10-year buried pipe B2.1.5 inspection frequency.
The Buried Piping and Tanks Inspection Program LRA Section
- 15. will be revised to specify a 10-year inspection B2.1.5 frequency for Diesel Fuel Oil Storage Tank T-44.
The Buried Piping and Tanks Inspection Program will be revised to include a review of previous LRA Section
- 16. buried piping issues to determine possible B2.1.5 susceptible locations.
Page 4 of 13
Commitment Source The Bus Duct Inspection Program will be a new program consisting of the appropriate ten elements described in Appendix A of NUREG-1800, Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants. The purpose of this aging management program will be to demonstrate, for in-scope non-segregated bus ducts, that the aging effects LRA Section
- 17. caused by ingress of moisture or contaminants B2.eto (dust and debris), insulation degradation caused B2.1.6 by heat or radiation in the presence of oxygen, and bolt relaxation caused by thermal cycling will be adequately managed so that there is reasonable assurance that the non-segregated bus ducts will perform their intended function in accordance with the current licensing basis during the period of extended operation.
The BWR Feedwater Nozzle Program will be enhanced so that the parameters monitored and LRA Section
- 18. inspected are consistent with the B2.1.8 recommendations of GE NE-523-A71-0594-A, Revision 1.
The BWR Feedwater Nozzle Program will be enhanced so the regions being inspected, LRA Section examination techniques, personnel qualifications, B2.1 .8
- 19. and inspection schedule are consistent with the recommendations of GE NE-523-A71-0594-A, Revision 1.
Page 5 of 13
Commitment Source The BWR Feedwater Nozzle Program will be enhanced so that inspections will be scheduled B2S18
- 20. per recommendations of GE NE-523-A71-0594- .1.
A, Revision 1.
The repair/replacement guidelines in BWRVIP- LRA Section 16, 19, 44, 45, 50, 51, 52, 57, and 58 will be B212
- 21. added, as applicable, to the MNGP BWR Vessel .1.1 Internals Program.
A one time inspection will be performed to monitor the effects of corrosion on select portions LRA Section
- 22. of closed-cycle cooling water systems that B2.1.13 perform a pressure integrity intended function.
The MNGP Compressed Air Monitoring Program procedures will be revised to include corrective action requirements if the acceptance limits for water vapor, oil content, or particulate are not LRA Section
- 23. met. Also, the acceptance criteria for oil content B2.1.14 testing will be clarified and the basis for the acceptance limits for the water vapor, oil content, and particulate tests will be provided.
The MNGP Compressed Air Monitoring Program will be revised to include inspection of air LRA Section
- 24. distribution piping based on the B2.1.14 recommendations of EPRI TR-108147.
Page 6 of 13
Commitment Source The MNGP Electrical Cables & Connections Not Subject To 10 CFR 50.49 Environmental Qualification Requirements Program will be implemented as a new program consistent with the recommendations of NUREG-1801 Chapter LRA Section
- 25. X1 Program X1.E1. The program will manage the B2.1.15 aging of conductor insulation material on cables, connectors, and other electrical insulation materials that are installed in an adverse localized environment caused by heat, radiation, or moisture.
The Electrical Cables Not Subject to 10 CFR 50.49 Environmental Qualification Requirements Used in Instrumentation Circuits Program will be LRA Section
- 26. implemented as a new program. With B2.1.16 exceptions, it will be consistent with the recommendations of NUREG-1801 Chapter Xl Program XL.E2.
The MNGP Fire Protection Program will be revised to include a visual inspection of the halon fire suppression system to detect any signs of LRA Section
- 27. degradation, such as corrosion and mechanical B2 S117 damage. This visual inspection will provide aging .1.
management for external surfaces of the halon fire suppression system.
Page 7 of 13
Commitment Source The fire protection program plan document will be revised to include qualification criteria for individuals performing visual inspections of
- 28. penetration seals, fire barriers, and fire doors. B2.1.17 The qualification criteria will be in accordance with VT-1 or equivalent and VT-3 or equivalent, as applicable.
The MNGP Fire Water System Program implementing procedures will be revised to include the extrapolation of inspection results to LRA Section
- 29. below grade fire water piping with similar B2.1.18 conditions that exist within the above grade fire water piping.
The MNGP Fire Water System Program sprinkler heads will be inspected and tested per NFPA requirements or replaced before the end of the 50-year sprinkler head service life and at 10-year LRA Section
- 30. intervals thereafter during the extended period of B2.1.18 operation to ensure that signs of degradation, such as corrosion, are detected in a timely manner.
Verify the procedures to be used for aging management activities of the Fire Water System LRA Section
- 31. apply testing in accordance with applicable NFPA B2.1.18 codes and standards. Revise the relevant procedures as appropriate.
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Commitment Source The MNGP procedures related to the Diesel Fuel Oil System will be revised to include LRA Section
- 32. requirements to check for general, pitting, B2.1 .20 crevice, galvanic, microbiological influenced corrosion (MIC), and cracking.
Revise MNGP Fuel Oil Chemistry Program procedures to require tank draining, cleaning, and inspection if deemed necessary based on LRA Section 33 the trends indicated by the results of the diesel B2.1 .20 fuel oil analysis, or as recommended by the system engineer based on equipment operating experience.
Write procedure or revise existing procedures in the MNGP Fuel Oil Chemistry Program to require LRA Section
- 34. periodic tank inspections of the diesel fuel oil B2.1.20 tanks.
The MNGP Inaccessible Medium Voltage (2 kV to 34.5 kV) Cables Not Subject to 10 CFR 50.49 EQ Requirements Program will be implemented LRA Section
- 35. as a new program consistent with the B2.1.21 recommendations of NUREG-1 801 Chapter XI Program XL.E3.
Page 9 of 13
Commitment Source The Inspection of Overhead Heavy Load & Light Load (Related to Refueling) Handling Systems LRA Section
- 36. Program will be enhanced to specify a five-year B2.1 .22 inspection frequency for the fuel preparation machines.
The MNGP One-Time Inspection Program will be implemented as a new program consistent with the recommendations of NUREG-1801 Chapter Xl Program M32, "One-Time Inspection." This program will include measures to verify the effectiveness of the following aging management LRA Section
- 37. programs: Plant Chemistry Program B2.1.23 Fuel Oil Chemistry Program This program will also confirm the absence of age degradation in selected components (e.g.,
flow restrictors, venturis) within License Renewal scope.
The MNGP Protective Coating Maintenance and Monitoring Program procedures will be updated LRA Section
- 38. to include inspection of all accessible painted B2.1.27 surfaces inside containment.
The MNGP Protective Coating Maintenance and Monitoring Program will be revised to include a LRA Section
- 39. pre-inspection review of the previous two B2.1 .27 inspection reports so that trends can be identified.
Page 10 of 13
Commitment Source The MNGP Protective Coating Maintenance and Monitoring Program implementation procedures LRA Section
- 40. will be revised to include provisions for analysis B2.1.27 of suspected reasons for coating failure.
MNGP intends to use the Integrated Surveillance Program during the period of extended operation LRA Section
- 41. by implementing the requirements of BWRVIP- B2.1.29 116, which is currently being reviewed by the NRC.
The MNGP Selective Leaching of Materials Program will be implemented as a new program consistent, with exceptions, to the recommendations of NUREG-1801 Chapter Xl Program M33, "Selective Leaching of Materials."
The program will be developed and implemented before the start of the period of extended operation. The program includes a one-time LRA Section
- 42. visual inspection and hardness measurement of . .
selected components that are susceptible to selective leaching. In situations where hardness testing is not practical, a qualitative method by other NDE or metallurgical methods will be used to determine the presence and extent of selective leaching. The program will determine if selective leaching is occurring for selected components.
Page 11 of 13
Commitment Source The Structures Monitoring Program will be expanded, as necessary, to include inspections LRA Section 43 of structures and structural elements in scope for B32.1.31 License Renewal that are not inspected as part of another aging management program.
Implementing procedures for the Structures Monitoring Program will be enhanced to ensure LRA Section
- 44. that structural inspections are~performed on B2.1.31 submerged portions of the intake structure from the service water bays to the wing walls Implementing procedures for the Structures Monitoring Program will be revised to include the LRA Section 45 monitoring/inspection parameters for structural B2.1ct1 components within the scope of License .1.31 Renewal.
The Structures Monitoring Program will be enhanced to include a requirement to sample LRA Section
- 46. ground water for pH, chloride concentration and B2.1.31 sulfate concentration.
The Structures Monitoring Program will be enhanced to include concrete evaluations of LRA Section
- 47. inaccessible areas if degradation of accessible B2.1.31 areas is detected.
Page 12 of 13
Commitment Source Implementing procedures for the Structures Monitoring Program will be enhanced to include LRA Section
- 48. acceptance criteria for structural inspections of B2.1.31 submerged portions of the Intake Structure.
Implementing instructions and procedures for the System Condition Monitoring Program will be LRA Section
- 49. revised to describe specific age degradation B2.1.32 parameters to be monitored and inspected.
Acceptance criteria will also be included.
Incorporate requirements for inclusion of NUREG/CR-6260 locations in implementing LRA Section
- 50. procedures for the MNGP Thermal Fatigue B3.2 Monitoring Program.
Page 13 of 13