Letter Sequence Other |
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TAC:MD9990, Clarify Application of Setpoint Methodology for LSSS Functions (Approved, Closed) |
Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance, Acceptance
- Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement
Administration
- Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance
- Meeting, Meeting, Meeting, Meeting, Meeting, Meeting
Results
Other: L-MT-08-091, Calculation 0801040.301, Steam Dryer Outer Hood Submodel Analysis., L-MT-09-002, Response to NRC Probabilistic Risk Assessment (PRA) Branch Requests for Additional Information (Rais) Dated December 5, 2008, L-MT-09-003, Response to NRC Environmental Branch Requests for Additional Information (Rais) Dated December 18, 2008, L-MT-09-004, Enclosure 1 (Continued) to L-MT-09-004, NSPM Response to Containment & Ventilation Branch RAI Number 2, Copy of MNGP Appr T0406 Data Transmittal Pages 1 of 538 Through Pages 538 of 538, L-MT-09-026, Calculation 0000-0081-6958 MNGP-PRNMS-APRM Calc-2008-NP, Rev. 1, Average Power Range Monitor Selected Prnm Licensing Setpoints - EPU Operation (Numac), L-MT-09-027, Extended Power Uprate: Response to Instrumentation and Controls Branch RAI No. 3 Dated April 6, 2009, L-MT-09-044, Extended Power Uprate: Response to NRC Mechanical and Civil Engineering Review Branch (Emcb) Requests for Additional Information (Rais) Dated March 28, 2009, L-MT-09-049, Drawing C.5-2007, Revision 15, Failure to Scram, L-MT-09-073, Extended Power Uprate: Response to NRC Containment and Ventilation Review Branch (Scvb) Requests for Additional Information (Rais) Dated July 2, 2009 and July 14, 2009, L-MT-09-083, Extended Power Uprate: Limit Curves Requested by the Mechanical and Civil Review Branch (Emcb) Associated with Requests for Additional Information (Rais) Dated March 20, 2009, L-MT-09-088, Extended Power Uprate: Revision to Clarify Text in Enclosures 5 and 7 of L-MT-08-052, L-MT-09-097, Extended Power Uprate: Acknowledgement of NRC Review Delay, L-MT-10-025, Extended Power Uprate (Epu): Response to NRC-NSPM February 25, 2010 Conference Call, L-MT-10-072, Extended Power Uprate: Updates to Docketed Information, L-MT-11-044, Uprate (Epu): Update on EPU Commitments, L-MT-12-056, WCAP-17549-NP, Rev. 0, Monticello Replacement Steam Dryer Structural Evaluation for High-Cycle Acoustic Loads Using ACE, L-MT-12-090, Westinghouse, LTR-A&SA-12-8, Rev. 1, Attachment B, Recommendations for Inspections of the Monticello Replacement Steam Dryer., L-MT-12-114, Drawing C.5-2007, Rev. 17, Failure to Scram, L-MT-13-020, Enclosure 1 - Responses to the Gap Analysis, L-MT-13-029, Enclosure 14 to L-MT-13-029 - WCAP-17716-NP, Revision 0, Benchmarking of the Acoustic Circuit Enhanced Revision 2.0 for the Monticello Steam Dryer Replacement Project., L-MT-13-091, WCAP-17716-NP, Revision 1 - Benchmarking of the Acoustic Circuit Enhanced Revision 2.0 for the Monticello Steam Dryer Replacement Project, Enclosure 14, L-MT-13-092, Extended Power Uprate (Epu): Completion of EPU Commitments, Proposed License Conditions and Revised Power Ascension Test Plan, L-MT-13-096, GE-MNGP-AEP-3304R1, Enclosure 4, NEDC-33435 Corrected Pages, L-MT-13-126, Enclosure 3, GE-MNGP-AEP-3306, Enclosure 2 GEH Response to Mella+ Eicb RAI and Affidavit, L-MT-14-023, Maximum Extended Load Line Limit Analysis Plus: Technical Specification Clarifications, L-MT-15-074, Enclosure 7, WCAP-18604-NP, Revision 0, Monticello EPU Main Steam Line Strain Data Evaluation Report., L-MT-16-017, Revised Commitment to Reconcile Analysis of Bypass Voiding for Transition to Areva Analysis Methodology, L-MT-16-071, Submittal of 2016 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46, ML083230111, ML083400402, ML083500575, ML083570610, ML083590127, ML090710680, ML090710683, ML090710684, ML091120578, ML091140470, ML091410121, ML091410122, ML091410123, ML091410124, ML091760769, ML092290250, ML092810554, ML093160816, ML093220925, ML093220964, ML093620024, ML100280558... further results
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MONTHYEARML0907106832008-02-17017 February 2008 Enclosure 1 (Continued) to L-MT-09-004, NSPM Response to Containment & Ventilation Branch RAI Number 2, Attachment 1-1g Through End of Encl. 1 Project stage: Other ML13064A4352008-03-20020 March 2008 CA-95-075, Main Steam Line High Flow Setpoint, Attachment 4 Project stage: Other ML0914101242008-08-11011 August 2008 Monticello - Calculation CA-08-050, Rev. 0, Instrument Setpoint Calculation - Average Power Range Monitor (APRM) Non-Flow Eiased Prnm Setpoints for Cl Tp and EPU Project stage: Other L-MT-08-091, Calculation 0801040.301, Steam Dryer Outer Hood Submodel Analysis.2008-10-31031 October 2008 Calculation 0801040.301, Steam Dryer Outer Hood Submodel Analysis. Project stage: Other ML0832301122008-10-31031 October 2008 NEDC-33322-NP, Revision 3, Monticello Nuclear Generating Plant, Safety Analysis Report, Constant Pressure Power Uprate. Project stage: Request ML0832301112008-11-0505 November 2008 Monticello Nuclear Generating Plant, License Amendment Request: Extended Power Uprate Project stage: Other ML0832301142008-11-0505 November 2008 Monticello Nuclear Generating Plant, Steam Dryer Dynamic Stress Evaluation. Project stage: Request ML0834003662008-12-0202 December 2008 Extended Power Uprate Acceptance Review Questions on Probabilistic Risk Assessment Issues Project stage: Acceptance Review ML0834004022008-12-0505 December 2008 Extended Power Uprate - Monticello - Request to Supplement the Application in the Probabilistic Risk Assessment Area Project stage: Other ML0835000992008-12-11011 December 2008 Monticello Extended Power Uprate (Usnrc TAC MD9990): Acceptance Review Supplement Regarding Steam Dryer Outer Hood Submodel Analysis Project stage: Supplement ML0835303022008-12-16016 December 2008 Draft Request for Additional Information, Environmental Issues of EPU Application Project stage: Draft RAI ML0936200242008-12-18018 December 2008 Report 0800760.401, Rev. 1, Flaw Evaluation and Vibration Assessment of Existing Monticello Steam Dryer Flaws for Extended Power Uprate. Project stage: Other ML0835005752008-12-18018 December 2008 Letter Finding 11/5/08 Application for Amendment Acceptable for Review Project stage: Other ML0835309982008-12-18018 December 2008 EPU Application - Additional RAI Question Regarding an Environmental Issue Project stage: RAI ML0835310022008-12-18018 December 2008 Proposed Eou Amendment - Revised RAI Re. Containment Analysis Project stage: RAI ML0914101222008-12-18018 December 2008 Monticello - Calculation CA-95-075, Revision 1, Main Steam Line High Flow Setpoint Project stage: Other ML0914101212008-12-19019 December 2008 Monticello - Calculation CA-95-073, Revision 4, Reactor Low Water Level SCRAM Setpoint Project stage: Other ML0835901272009-01-14014 January 2009 Letter Conveying Determination That Enclosure 5 of 11/5/08 Application for EPU Amendment Contains Proprietary Information and Withheld from Public Disclosure Project stage: Other ML0835706102009-01-26026 January 2009 Letter Conveying Determination That Enclosure 11 of 11/5/08 Application for EPU Amendment Contains Proprietary Information and Is Withheld from Public Disclosure Project stage: Other L-MT-09-003, Response to NRC Environmental Branch Requests for Additional Information (Rais) Dated December 18, 20082009-01-29029 January 2009 Response to NRC Environmental Branch Requests for Additional Information (Rais) Dated December 18, 2008 Project stage: Other L-MT-09-005, Revision to Attachment 1 of Enclosure 17 of MNGP License Amendment Request for Extended Power Uprate2009-02-0404 February 2009 Revision to Attachment 1 of Enclosure 17 of MNGP License Amendment Request for Extended Power Uprate Project stage: Request L-MT-09-002, Response to NRC Probabilistic Risk Assessment (PRA) Branch Requests for Additional Information (Rais) Dated December 5, 20082009-02-0404 February 2009 Response to NRC Probabilistic Risk Assessment (PRA) Branch Requests for Additional Information (Rais) Dated December 5, 2008 Project stage: Other ML0904204852009-02-11011 February 2009 Draft RAI from Materials Engineering Re. Proposed Extended Power Uprate Amendment Project stage: Draft RAI ML0907106792009-02-17017 February 2009 Monticello, Response to NRC Containment & Ventilation Branch Request for Additional Information (Rals) Dated December 18, 2008 Project stage: Request ML0907106802009-02-17017 February 2009 Monticello, Enclosure 1 to L-MT-09-004, NSPM Response to Containment & Ventilation Branch RAI Number 1 Dated December 18, 2008, Cover Through Copy of MNGP Appr T0406 Data Transmittal Page 424 of 424 Project stage: Other L-MT-09-004, Enclosure 1 (Continued) to L-MT-09-004, NSPM Response to Containment & Ventilation Branch RAI Number 2, Copy of MNGP Appr T0406 Data Transmittal Pages 1 of 538 Through Pages 538 of 5382009-02-17017 February 2009 Enclosure 1 (Continued) to L-MT-09-004, NSPM Response to Containment & Ventilation Branch RAI Number 2, Copy of MNGP Appr T0406 Data Transmittal Pages 1 of 538 Through Pages 538 of 538 Project stage: Other ML0907106842009-02-17017 February 2009 Enclosures 2 - 4: NSPM Response to Containment & Ventilation Branch RAI Numbers 2, 3 and 4 Dated December 18, 2008 Project stage: Other L-MT-09-018, Response to NRC Steam Generator Tube Integrity & Chemical Engineering Branch Request for Additional Information (RAI) Dated February 11, 20092009-02-24024 February 2009 Response to NRC Steam Generator Tube Integrity & Chemical Engineering Branch Request for Additional Information (RAI) Dated February 11, 2009 Project stage: Request ML0907100912009-03-11011 March 2009 Conveying Draft RAI Questions from the Instrumentation and Controls Branch Regarding the Proposed Extended Power Uprate Amendment Project stage: Draft RAI ML0907200572009-03-12012 March 2009 Conveys Draft RAI Regarding Fire Protection for the Proposed Extended Power Uprate Amendment Project stage: Draft RAI ML0907800062009-03-18018 March 2009 Draft RAI from Probabilistic Risk Assessment Licensing Branch on the Proposed Extended Power Uprate Amendment Project stage: Draft RAI ML0907800042009-03-18018 March 2009 Conveys Draft RAI by the PRA Licensing Branch on the Proposed EPU Amendment Project stage: Draft RAI ML0907809032009-03-19019 March 2009 Conveys Draft RAI Provided by the Containment and Ventilation Branch on the Proposed Extended Power Uprate Amendment Project stage: Draft RAI ML0907809092009-03-19019 March 2009 RAI from the Containment and Ventilation Branch the Proposed Extended Power Uprate Amendment Project stage: RAI L-MT-09-017, Extended Power Uprate: Response to NRC Reactor Systems Branch & Nuclear Performance & Code Review Branch Request for Additional Information (RAI) Dated January 16, 20092009-03-19019 March 2009 Extended Power Uprate: Response to NRC Reactor Systems Branch & Nuclear Performance & Code Review Branch Request for Additional Information (RAI) Dated January 16, 2009 Project stage: Request ML0908200312009-03-20020 March 2009 Draft RAI Re. Health Physics Issues for the Proposed Extended Power Uprate Amendment Project stage: Draft RAI ML0908200992009-03-23023 March 2009 Draft RAI from the Balance of Plant Branch Re the Proposed Amendment on Extended Power Uprate Project stage: Draft RAI ML0908800022009-03-28028 March 2009 Second Portion of Draft RAI from the Mechanical and Civil Engineering Branch Regarding the Proposed Extended Power Uprate Amendment Project stage: Draft RAI ML0908800032009-03-28028 March 2009 Draft RAI from the Electrical Engineering Branch Re. the Proposed Extended Power Uprate Amendment for Monticello Project stage: Draft RAI ML0908800012009-03-29029 March 2009 Additional Draft RAI Questions from the Containment and Ventilation Branch Proposed EPU Amendment for Monticello Project stage: Draft RAI ML0910300172009-04-0606 April 2009 Conveys an Additional EPU Draft RAI Question from Instrumentation and Controls Branch Project stage: Draft RAI ML0910300212009-04-0606 April 2009 Draft RAI Question from Instrumentation and Controls Branch Re. Proposed EPU Amendment Project stage: Draft RAI ML0911205782009-04-22022 April 2009 Request for Audit of Implementation of Long-Term Stability Solution Project stage: Other L-MT-09-025, Extended Power Uprate: Response to NRC Reactor Systems Branch and Nuclear Performance & Code Review Branch Request for Additional Information (RAI) Dated February 23, 20092009-04-22022 April 2009 Extended Power Uprate: Response to NRC Reactor Systems Branch and Nuclear Performance & Code Review Branch Request for Additional Information (RAI) Dated February 23, 2009 Project stage: Request ML0911902092009-04-29029 April 2009 Transmit Revised Draft RAI from the Probabilistic Risk Assessment Licensing Branch on the Proposed Extended Power Uprate Amendment Project stage: Draft RAI ML0914101232009-05-0606 May 2009 Monticello - Calculation 96-054, Rev 5, Turbine Stop Valve Closure/Generator Load Reject Scram Bypass Project stage: Other ML0911404702009-05-0707 May 2009 Determination That Submitted Information Can Be Withheld from Public Disclosure Project stage: Other ML0914101202009-05-13013 May 2009 Monticello - Extended Power Uprate: Response to NRC Instrumentation & Controls Branch Request for Additional Information Dated March 11, 2009, and April 6, 2009, and Fire Protection Branch RAIs Dated March 12, 2009 Project stage: Request L-MT-09-045, Extended Power Uprate: Response to NRC Electrical Engineering Review Branch (Eeeb) Request for Additional Information (RAI) Dated March 28, 20092009-05-26026 May 2009 Extended Power Uprate: Response to NRC Electrical Engineering Review Branch (Eeeb) Request for Additional Information (RAI) Dated March 28, 2009 Project stage: Request L-MT-09-029, Extended Power Uprate: Response to NRC Probabilistic Risk Assessment (PRA) Licensing Branch Request for Additional Information (RAI) Dated April 29, 20092009-05-29029 May 2009 Extended Power Uprate: Response to NRC Probabilistic Risk Assessment (PRA) Licensing Branch Request for Additional Information (RAI) Dated April 29, 2009 Project stage: Request 2009-02-24
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Category:Letter type:L
MONTHYEARL-MT-24-038, Subsequent License Renewal Application Response to Request for Additional Information - 3rd Round RAI2024-10-15015 October 2024 Subsequent License Renewal Application Response to Request for Additional Information - 3rd Round RAI L-MT-24-025, Application to Revise Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements2024-09-26026 September 2024 Application to Revise Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements L-MT-24-029, Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information-Supplement to Set 1 Part 2 and Response to 2ci Round RAI2024-09-13013 September 2024 Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information-Supplement to Set 1 Part 2 and Response to 2ci Round RAI L-MT-24-028, Response to RCI for RR-017 ISI Impracticality2024-08-28028 August 2024 Response to RCI for RR-017 ISI Impracticality L-MT-24-022, – Preparation and Scheduling of Operator Licensing Examinations2024-07-0909 July 2024 – Preparation and Scheduling of Operator Licensing Examinations L-MT-24-019, Submittal of ASME Section XI, Section IWB-3720 Analytical Evaluation in Accordance with 10 CFR 50.55a(b)(2)(xliii)2024-06-10010 June 2024 Submittal of ASME Section XI, Section IWB-3720 Analytical Evaluation in Accordance with 10 CFR 50.55a(b)(2)(xliii) L-MT-24-017, Response to Request for Additional Information Regarding License Amendment Request to Revise Monticello Technical Specification Surveillance Requirement 3.8.6.6 (EPID-L-2023-LLA-01602024-06-0404 June 2024 Response to Request for Additional Information Regarding License Amendment Request to Revise Monticello Technical Specification Surveillance Requirement 3.8.6.6 (EPID-L-2023-LLA-0160 L-MT-24-015, Response to Request for Additional Information - Alternative Request VR-09 for OMN-172024-05-16016 May 2024 Response to Request for Additional Information - Alternative Request VR-09 for OMN-17 L-MT-24-013, 2023 Annual Radiological Environmental Operating Report2024-05-14014 May 2024 2023 Annual Radiological Environmental Operating Report L-MT-24-016, 2023 Annual Report of Individual Monitoring for the Monticello Nuclear Generating Plant (MNGP)2024-05-0808 May 2024 2023 Annual Report of Individual Monitoring for the Monticello Nuclear Generating Plant (MNGP) L-MT-24-004, Submittal of 10 CFR 72.48 Report for Monticello Nuclear Generating Plant (MNGP)2024-04-17017 April 2024 Submittal of 10 CFR 72.48 Report for Monticello Nuclear Generating Plant (MNGP) L-MT-24-002, Submittal of Revision 41 to the Updated Safety Analysis Report2024-04-17017 April 2024 Submittal of Revision 41 to the Updated Safety Analysis Report L-MT-24-006, Subsequent License Renewal Application Annual Update 1 and Supplement 92024-02-29029 February 2024 Subsequent License Renewal Application Annual Update 1 and Supplement 9 L-MT-24-007, Response to NRC Request for Additional Information on Proposed Inservice Inspection Alternative RR-002 for the Sixth Ten-Year ISI Interval2024-02-15015 February 2024 Response to NRC Request for Additional Information on Proposed Inservice Inspection Alternative RR-002 for the Sixth Ten-Year ISI Interval L-MT-24-001, 10 CFR 50.55a Request RR-017 - Inservice Inspection (ISI) Impracticality in Accordance with 10 CFR 50.55a(g)(5)(iii) During the Fifth Ten-Year Interval2024-01-30030 January 2024 10 CFR 50.55a Request RR-017 - Inservice Inspection (ISI) Impracticality in Accordance with 10 CFR 50.55a(g)(5)(iii) During the Fifth Ten-Year Interval L-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 2024-09-26
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&XcelEnergy@ Monticello Nuclear Generating Plant 2807 W County Rd 75 Monticello, MN 55362 August 30, 2011 L-MT-1 1-044 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC' 20555-0001 Monticello Nuclear Generating Plant Docket 50-263 Renewed License No. DPR-22
Subject:
Monticello Extended Power Uprate (EPU): Update on EPU Commitments (TAC MD9990)
References:
- 1) Letter from Northern States Power Company, a Minnesota corporation (NSPM), d/b/a Xcel Energy to Document Control Desk, "License Amendment Request: Extended Power Uprate (TAC MD9990)," L-MT-08-052, dated November 5, 2008. (ADAMS Accession No. ML083230111)
- 2) Letter from T. J. O'Connor (NSPM), to Document Control Desk (NRC),
"Monticello Extended Power Uprate: Updates to Docketed Information (TAC MD9990)," L-MT-10-072, dated December 21, 2010. (ADAMS Accession No. ML103570026)
Pursuant to 10 CFR 50.90, the Northern States Power Company, a Minnesota corporation (NSPM), doing business as Xcel Energy, requested in Reference 1 an amendment to the Monticello Nuclear Generating Plant (MNGP) Renewed Operating License (OL) and Technical Specifications (TS) to increase the maximum authorized power level from 1775 megawatts thermal (MWt) to 2004 MWt.
The purpose of this letter is to provide the NRC with the status of analyses and commitments previously provided to the NRC for the MNGP extended power uprate (EPU). Updates are provided in the following enclosures:
Enclosure 1 - Feedwater/Condensate Events and Feedwater/Condensate Pump Area Heat Load Enclosure 2 - Modification of Pipe Support TWH-143 Enclosure 3 - Appendix R Modifications to Vent and Purge Valves Enclosure 4 - Summary of Extended Power Uprate Commitments 00
Document Control Desk Page 2 The changes made in herein do not revise the no significant hazards consideration (NSHC) provided in Reference 2.
In accordance with 10 CFR 50.91(b), a copy of this application supplement, without enclosures, is being provided to the designated Minnesota Official.
Summary of Commitments This letter makes no new commitments. This letter closes commitments and revises commitments associated with the EPU project. See Enclosure 4 for details. The commitment summary includes whether the commitment is new, revised, or completed.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on: August 30, 2011
-T,15-0 Timothy J. O'Connor
^ Site Vice-President Monticello Nuclear Generating Plant Northern States Power Company-Minnesota Enclosures (4) cc: Administrator, Region III, USNRC (w/o enclosures)
Resident Inspector, Monticello Nuclear Generating Plant, USNRC (w/o enclosures)
Project Manager, Monticello Nuclear Generating Plant, USNRC Minnesota Department of Commerce (w/o enclosures)
L-MT-1 1-044 ENCLOSURE 1 FEEDWATER/CONDENSATE EVENTS AND FEEDWATER/CONDENSATE PUMP AREA HEAT LOAD 2 pages follow
L-MT-1 1-044 FEEDWATER/CONDENSATE EVENTS AND FEEDWATER/CONDENSATE PUMP AREA HEAT LOAD
Background
In Reference E1-1, Northern States Power Company, a Minnesota corporation (NSPM),
d/b/a Xcel Energy provided a license amendment request (LAR) for the Monticello Nuclear Generating Plant. The Reference E1-1 LAR requested approval to increase the maximum authorized power level from 1775 megawatts thermal (MWt) to 2004 MWt.
In Reference E1-2, NSPM provided a response to NRC requests for additional information (RAIs). As part of the response to RAI 2.12.2, NSPM made the following commitment:
NSPM will perform an analysis prior to RF025 to predict combined Condensate and Feedwatersystem performance for normal operation and for transientsincluding Single Feedwaterpump trip, FeedwaterControl System Failureand Single Condensate Pump Trip. Acceptance criteria will include adequate margin to preclude loss of both reactorfeedwaterpumps from low suction pressure or flow.
In Reference E1-3, NSPM provided a response to NRC RAIs. As part of the response to RAI 35, NSPM made the following commitment:
NSPM commits to evaluating the changes in condensate and feed pump area heat load to confirm temperaturesremain within design limits prior to RF025. If necessary,modifications to the HVAC system for this area will be implemented to maintain these areas within the design limits.
Both of these commitments have not been met as MNGP entered refueling outage 25 (RF025) on March 5, 2011 and the subject analyses and evaluations have not been completed.
Discussion Both commitments require calculations and analyses to complete the commitment requirements. Depending on the outcome of the evaluations further modifications may also be required.
Each commitment has been reviewed for change by the Regulatory Commitment Change process. The results of this review indicated that both commitments may be changed without prior consent of the NRC. NSPM has determined that both commitments are not required to be implemented until MNGP ascends to Extended Power Uprate (EPU) conditions. Since EPU is not yet approved for MNGP, there is no safety concern with modifying the due date for these commitments.
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L-MT-1 1-044 Conclusion Based on the above, NSPM is modifying the commitments to change the commitment due date from "prior to RF025" to "prior to EPU implementation." No change of substance of the commitment is proposed only the schedule for completion is changed.
Based on this change each commitment will read as follows:
NSPM will perform an analysisprior to EPU implementation to predict combined Condensate and Feedwatersystem performance for normal operationand for transients including Single Feedwaterpump trip, Feedwater Control System Failure and Single Condensate Pump Trip. Acceptance criteria will include adequate margin to preclude loss of both reactorfeedwaterpumps from low suction pressure or flow.
NSPM commits to evaluating the changes in condensate and feed pump area heat load to confirm temperaturesremain within design limits prior to EPU implementation. If necessary, modifications to the HVAC system for this area will be implemented to maintain these areas within the design limits.
References:
El-1 Letter from Northern States Power Company, a Minnesota corporation (NSPM),
d/b/a Xcel Energy to Document Control Desk, "License Amendment Request:
Extended Power Uprate (TAC MD9990)," L-MT-08-052, dated November 5, 2008. (ADAMS Accession No. ML083230111)
E1-2 Letter from T. J. O'Connor (NSPM), to Document Control Desk (NRC),
"Monticello Extended Power Uprate: Response to NRC Balance of Plant Review Branch (SBPB) Request for Additional Information (RAI) dated March 23, 2009 (TAC No. MD9990)," L-MT-09-046, dated June 12, 2009. (ADAMS Accession No. ML091670410)
E1-3 Letter from T. J. O'Connor (NSPM), to Document Control Desk (NRC),
"Monticello Extended Power Uprate: Response to NRC Containment and Ventilation Review Branch (SCVB) Request for Additional Information (RAI) dated March 19, 2009, and March 26, 2009 (TAC No. MD9990)," L-MT-09-048, dated July 13, 2009. (ADAMS Accession No. ML092170404)
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L-MT-1 1-044 ENCLOSURE 2 MODIFICATION OF PIPE SUPPORT TWH-143 I page follows
L-MT-1 1-044 MODIFICATION OF PIPE SUPPORT TWH-143
Background
In Reference E2-1, Northern States Power Company, a Minnesota corporation (NSPM),
d/b/a Xcel Energy provided a license amendment request (LAR) for the Monticello Nuclear Generating Plant. The Reference E2-1 LAR requested to increase the maximum authorized power level from 1775 megawatts thermal (MWt) to 2004 MWt.
In Reference E2-2, NSPM provided a response to NRC requests for additional information (RAIs). As part of the response to RAI 12(b), NSPM made the following commitment:
Confirmation that modification of support TWH- 143 is complete will be provided to the NRC priorto implementation of the EPU license amendment request.
This commitment has been completed as indicated below.
Discussion As indicated in reference E2-2, NSPM performed a series of calculations and analyses to determine the acceptability of stresses in piping systems, i.e. the piping system meets code requirements. As a result of the analyses for Torus attached piping, support TWH-143 was identified as requiring modification to meet acceptable stress levels. Based on this NSPM developed and implemented a modification to replace TWH-143 with an adequate support.
The modification to TWH-143 was recently installed and post-maintenance tested satisfactorily.
Conclusion Based on the above, NSPM completed the commitment described above and is hereby notifying the NRC that the modification has been completed. Therefore, this commitment has been satisfied and is considered closed, with no further action required.
References:
E2-1 Letter from Northern States Power Company, a Minnesota corporation (NSPM),
d/b/a Xcel Energy to Document Control Desk, "License Amendment Request:
Extended Power Uprate (TAC MD9990)," L-MT-08-052, dated November 5, 2008. (ADAMS Accession No. ML083230111)
E2-2 Letter from T. J. O'Connor (NSPM), to Document Control Desk (NRC),
"Response to NRC Mechanical and Civil Engineering Review Branch (EMCB)
Requests for Additional Information (RAIs) dated March 28, 2009 (TAC MD9990)," L-MT-09-044, dated August 21, 2009. (ADAMS Accession No. ML092390332)
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L-MT-1 1-044 ENCLOSURE 3 APPENDIX R MODIFICATIONS TO VENT AND PURGE VALVES 2 Pages follow
L-MT-1 1-044 APPENDIX R MODIFICATIONS TO VENT AND PURGE VALVES
Background
In Reference E3-1 Northern States Power Company, a Minnesota corporation (NSPM),
d/b/a Xcel Energy provided a license amendment request (LAR) for the Monticello Nuclear Generating Plant. The Reference E3-1 LAR requested to increase the maximum authorized power level from 1775 megawatts thermal (MWt) to 2004 MWt.
In Reference E3-2, NSPM provided Licensee Event Report (LER) 2009-001, Revision 2.
In this LER NSPM identified that depending on initial conditions, a fire in the cable spreading room or control room, with or without a fire induced loss of off site power, could cause two in-series valves (containment purge and vent valves) to spuriously open leading to venting of containment. For certain design basis accident scenarios and 10 CFR 50 Appendix R events under Extended Power Uprate (EPU) conditions, containment accident pressure is required in order to ensure adequate net positive suction head (NPSH) is available for vessel injection and suppression pool cooling pumps. Venting of containment during this scenario could result in the loss of required NPSH for the #12 Core Spray (CS) and the #12 Residual Heat Removal (RHR) pumps.
With no operator action, inadequate NPSH could prevent vessel injection and/or suppression pool cooling. The station procedure for performing a shutdown from outside the control room did not contain any steps to require operators to ensure adequate NPSH was maintained.
Discussion As indicated in reference E3-2, to correct the condition NSPM would either evaluate the non-compliant manual actions as acceptable or correct the non-compliant manual actions via physical changes to the plant. Based on this, NSPM developed and implemented a modification to reroute the cabling associated with the purge and vent valves to eliminate the potential spurious opening of both valves from a single event.
The modification to the purge and vent valve cables was installed and post-maintenance tested satisfactorily during refueling outage 25 (RF025).
Conclusion Based on the above, NSPM completed the corrective action and is hereby notifying the NRC that the modification has been completed. No further impacts regarding the availability of containment accident pressure have been identified. Therefore, this condition has been satisfied and is considered closed, with no further action required.
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L-MT-1 1-044
References:
E3-1 Letter from Northern States Power Company, a Minnesota corporation (NSPM),
d/b/a Xcel Energy to Document Control Desk, "License Amendment Request:
Extended Power Uprate (TAC MD9990)," L-MT-08-052, dated November 5, 2008. (ADAMS Accession No. ML083230111)
E3-2 Letter from T. J. O'Connor (NSPM), to Document Control Desk (NRC), "LER 2009-001, Revision 2, "Containment Overpressure Not Ensured in the Appendix R Analysis," L-MT-10-070, dated December 22, 2010. (ADAMS Accession No. MLI103570034)
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L-MT-1 1-044 ENCLOSURE 4
SUMMARY
OF EXTENDED POWER UPRATE COMMITMENTS 4 Pages follow
L-MT-1 1-044 Summary of Extended Power Uprate Commitments Below is the complete list of NRC commitments for the Extended Power Uprate (EPU) project prior to issuance of this letter.
No. Letter No. Date Commitment text Status 1 L-MT-08-052 NSPM will inspect the steam dryer during Complete -
11/5/2008 the next refueling outage to confirm no performed in unexpected changes in crack length on the RF024.
steam dryer. (L-MT-10-046) 2 L-MT-09-017 The steady state bypass void fraction for the Complete -
3/19/2009 EPU core will be calculated using the provided in method described by the NSPM response to Cycle 25 NRC RAI SNPB-7 of L-MT-09-017. Supplemental Reload Licensing Report (SRLR).
(L-MT-10-046) 3 L-MT-09-043 NSPM will provide the evaluation of steam Deleted -
8/12/2009 dryer structural integrity to the NRC staff Commitment no prior to further increases in reactor power longer required.
when increasing to power levels above (L-MT-10-046)
CLTP.
4 L-MT-09-043 NSPM will perform outage steam dryer Active 8/12/2009 inspections based on the guidance of BWRVIP [Boiling Water Reactor Vessel Internals Project].
5 L-MT-09-044 Confirmation that Feedwater and Active 8/21/2009 Condensate pump and heater replacement modifications are complete and meet the code allowables will be provided to the NRC prior to implementation of the EPU license amendment request.
6 L-MT-09-044 Confirmation that modification of support Active 8/21/2009 TWH-143 is complete will be provided to the NRC prior to implementation of the EPU license amendment request.
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L-MT-1 1-044 7 L-MT-09-046 NSPM will perform an analysis prior to Active 6/12/2009 RF025 to predict combined Condensate and Feedwater system performance for normal operation and for transients including Single Feedwater pump trip, Feedwater Control System Failure and Single Condensate Pump Trip. Acceptance criteria will include adequate margin to preclude loss of both reactor feedwater pumps from low suction pressure or flow.
8 L-MT-10-072 Prior to implementation of EPU, the USAR Active 12/21/2010 will be revised to indicate that the Revised from emergency heat load of 24.7 MBTU/hr original in L-MT- occurs approximately 192 hours0.00222 days <br />0.0533 hours <br />3.174603e-4 weeks <br />7.3056e-5 months <br /> after 09-046 6/12/2009 shutdown.
9 L-MT-09-048 NSPM commits to evaluating the changes in Active 7/13/2009 condensate and feed pump area heat load to confirm temperatures remain within design limits prior to RF025. If necessary, modifications to the HVAC system for this area will be implemented to maintain these areas within the design limits.
10 L-MT-09-100 If NRR agrees to review the MELLLA+ Complete -
10/28/2009 [Maximum Extended Load Line Limit NRC Analysis Plus] LAR concurrent with the EPU acceptance of LAR, NSPM will commit in the MELLLA+ MELLLA+ LAR.
LAR to resolve the CAP section in the same (L-MT-10-046) manner as the issue is resolved for the delayed EPU amendment.
11 L-MT-10-046 As part of MNGP restart following Active 6/30/2010 installation of the replacement steam dryer, NSPM will implement the Power Ascension Test Plan found in Enclosure 1, Appendix 5 of L-MT-10-046.
Revised or Completed Commitments Commitment 6 is completed as described in Enclosure 2 Commitment 7 is revised as described in Enclosure 1 Commitment 9 is revised as described in Enclosure 1 Final List of EPU Commitments Based on these changes and the revised commitments associated with this letter the revised EPU commitments table is as follows:
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L-MT-1 1-044 Extended Power Uprate Commitments No. Letter No. Date Commitment text Status 1 L-MT-08-052 NSPM will inspect the steam dryer during the Complete 11/5/2008 next refueling outage to confirm no (L-MT-10-046) unexpected changes in crack length on the steam dryer.
2 L-MT-09-017 The steady state bypass void fraction for the Complete 3/19/2009 EPU core will be calculated using the method (L-MT-10-046) described by the NSPM response to NRC RAI SNPB-7 of L-MT-09-017.
3 L-MT-09-043 NSPM will provide the evaluation of steam Deleted 8/12/2009 dryer structural integrity to the NRC staff (L-MT-10-046) prior to further increases in reactor power when increasing to power levels above CLTP.
4 L-MT-09-043 NSPM will perform outage steam dryer Active 8/12/2009 inspections based on the guidance of BWRVIP.
5 L-MT-09-044 Confirmation that Feedwater and Active 8/21/2009 Condensate pump and heater replacement modifications are complete and meet the code allowables will be provided to the NRC prior to implementation of the EPU license amendment request.
6 L-MT-09-044 Confirmation that modification of support Complete 8/21/2009 TWH-143 is complete will be provided to the (L-MT-1 1-044)
NRC prior to implementation of the EPU license amendment request.
7 L-MT-11-044 NSPM will perform an analysis prior to EPU Active Enclosure 1 implementation to predict combined Revised from Condensate and Feedwater system original in L-MT- performance for normal operation and for 09-046 transients including Single Feedwater pump 6/12/2009 trip, Feedwater Control System Failure and Single Condensate Pump Trip. Acceptance criteria will include adequate margin to preclude loss of both reactor feedwater pumps from low suction pressure or flow.
8 L-MT-10-072 Prior to implementation of EPU, the USAR Active 12/21/2010 will be revised to indicate that the emergency Revised from heat load of 24.7 MBTU/hr occurs original in L-MT- approximately 192 hours0.00222 days <br />0.0533 hours <br />3.174603e-4 weeks <br />7.3056e-5 months <br /> after shutdown..09-046 6/12/2009 Page 3 of 4
L-MT-1 1-044 9 L-MT-1 1-044 NSPM commits to evaluating the changes in Active Enclosure 1 condensate and feed pump area heat load to Revised from confirm temperatures remain within design original in L-MT- limits prior to EPU implementation. If 09-048 necessary, modifications to the HVAC 7/13/2009 system for this area will be implemented to maintain these areas within the design limits.
10 L-MT-09-100 If NRR agrees to review the MELLLA+ LAR Complete 10/28/2009 concurrent with the EPU LAR, NSPM will (L-MT-10-046) commit in the MELLLA+ LAR to resolve the CAP section in the same manner as the issue is resolved for the delayed EPU amendment.
11 L-MT-10-046 As part of MNGP restart following installation Active 6/30/2010 of the replacement steam dryer, NSPM will implement the Power Ascension Test Plan found in Enclosure 1, Appendix 5 of L-MT-10-046.
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