Letter Sequence Supplement |
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TAC:ME3145, 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 ML0910300212009-04-0606 April 2009 Draft RAI Question from Instrumentation and Controls Branch Re. Proposed EPU Amendment 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 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 ML0911205782009-04-22022 April 2009 Request for Audit of Implementation of Long-Term Stability Solution Project stage: Other 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-24-022, – 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-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 2024-07-09
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XcelEnergy@ Monticello Nuclear Generating Plant 2807 W County Road 75 Monticello, MN 55362 WITHHOLD ATTCHMENT 2 OF ENCLOSURE 1 FROM PUBLIC DISCLOSURE UNDER 10 CFR 2.390 March 4, 2010 L-MT-10-017 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Monticello Nuclear Generating Plant Docket 50-263 Renewed License No. DPR-22
Subject:
Monticello MELLLA +: Supplemental Information Needed to Complete The Acceptance Review, (TAC ME3145)
References:
- 1) Letter from Northern States Power Company, a Minnesota corporation (NSPM), d/b/a Xcel Energy to Document Control Desk, "License Amendment Request: Maximum Extended Load Line Limit Analysis Plus," L-MT-1 0-003, dated January 21, 2010, TAC ME3145, Accession No. ML100280558.
- 2) Email from Peter Tam (NRC) to Lynne Gunderson, Gabor Salamon, Kurt Schaefer (Xcel), "Monticello MELLLA+ -
Supplemental Information Needed to Complete Acceptance Review," February 17, 2010, Accession No. ML100490043.
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 to allow operation within the Maximum Extended Load Line Limit Analysis Plus (MELLLA+) operating domain.
In Reference 2, the Nuclear Performance & Code Review Branch (SNPB) of the Nuclear Regulatory Commission (NRC) requests additional information in order to complete the acceptance review of the Reference 1 MELLLA+ submittal. provides the responses to acceptance review requests for additional information (RAIs) 2, 5 and 6 from Reference 2, and refers to for the responses to acceptance review RAIs 1, 3 and 4.
COO0 N)R\Z
Document Control Desk Page 2 contains responses provided by GE Hitachi Nuclear Energy (GEH) and has three enclosures. Enclosure 1 provides the responses for acceptance review RAIs 1, 3 and 4, and contains GEH proprietary information. NSPM requests that the proprietary information be withheld from public disclosure in accordance with 10 CFR 2.390(a)4, as authorized by 10 CFR 9.17(a)4. is a redacted non-proprietary version of Enclosure 1 with the GEH proprietary information removed, and is suitable for public disclosure. An affidavit supporting the request to withhold Enclosure 1 is provided in . Any comments with respect to the affidavit should be directed to James F. Harrison, GE Hitachi Nuclear Energy, 3901 Castle Hayne Road, Wilmington, NC 28401.
Summary of Commitments This letter makes no new commitments and no revisions to existing commitments.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on: March _ 2010 ite Vic sident Montic o uclear Generating Plant Northe n tates Power Company-Minnesota Attachments (2) cc: Administrator, Region Ill, USNRC Project Manager, Monticello Nuclear Generating Plant, USNRC Resident Inspector, Monticello Nuclear Generating Plant, USNRC Minnesota Department of Commerce
ATTACHMENT 1 SUPPLEMENTAL INFORMATION NEEDED TO COMPLETE THE ACCEPTANCE REVIEW FOR THE PROPOSED MELLLA+
AMENDMENT
L-MT-10-017 Page 1 of 8 NRC Acceptance Review RAI 1 Limitation 12.8 from the NRC staff's safety evaluation report (SER) for licensing topical report (LTR) NEDC-33006P, "General Electric Boiling Water Reactor Maximum Extended Load Line Limit Analysis Plus," (hereafter the M+LTR) requires submittal of the reactor pressure vessel fluence evaluation.
Section 3.2.1 of NEDC-33435P, "Safety Analysis Report for Monticello Maximum Extended Load Line Limit Analysis Plus," (hereafter the M+SAR) briefly describes the vessel and shroud fluence evaluation. Please provide a detailed description of the analysis including a list of assumptions, justification for the assumptions, and numerical results.
Response
The response to RAI 1 is contained within Attachment 2.
L-MT-10-017 Page 2 of 8 NRC Acceptance Review RAI 2 Section 3.3.6 of the M+SAR states that moisture carryover (MCO) will increase during operation at low flow in the MELLLA+ domain. For it to evaluate the applicability of several generic M+LTR dispositions, the NRC staff needs detailed information regarding the current MCO, the assumed MCO in the MNGP extended power uprate (EPU) licensing basis, and the sensitivity of the MCO to MELLLA+ operation, as evaluated. Describe the process by which steam separator-dryer test results are used to ensure acceptable operation. Please also include a discussion in terms of increased MCO and its impact on environmental qualification and turbine gamma shine.
Response
The original steam dryer MCO design cycle average value was 0.1% prior to Extended Power Uprate (EPU). The EPU analysis conservatively assumed a ten-fold increase in MCO to a cycle average value of 0.5% over the typical 0.05%
cycle average value that existed at power levels prior to EPU. The EPU analysis is considered the current MCO, because the MELLLA+ application is based on the assumption that EPU is implemented. MCO will be monitored, and plant operation controlled to maintain the plant within 0.5% cycle average value for MCO during both EPU and MELLLA+ operation. The potential MCO increases under MELLLA+ will be controlled to maintain MCO within the evaluated cycle average value of 0.5%.
MCO performance is evaluated by plant procedure. The procedure determines the moisture content in reactor steam based on comparison of Sodium-24 concentrations in reactor water and condensate demineralizer inlet. Section 2.12 of NEDC-33322P, Safety Analysis Report for Monticello Constant Pressure Power Uprate, provides a required EPU startup test to confirm steam separator-dryer performance is within limits by determining MCO during power ascension testing. Section 10.4.1 of NEDC-33435P, Rev 1, Safety Analysis Report for Monticello Maximum Extended Load Line Limit Analysis, discusses testing for MCO with MELLLA+. Plant procedures will control plant operation to maintain cycle average values within the limit of 0.5% MCO.
In a conference call with the NRC on February 19, 2010, NSPM agreed to provide further information on the assessments completed for EPU and MELLLA+ and point to locations where MCO information is located. Locations are provided below.
EPU Evaluation L-MT-08-041 dated June 3, 2008, Acceptance Review Supplemental Information Package 4, Accession No. ML081550640 provided a response with respect to the impact of EPU on MCO. Operating, shutdown and sky shine dose impacts were based on an evaluation that considered a ten-fold increase in MCO to an assumed value of 0.5% MCO for EPU. The letter notes that typical MCO values
L-MT-10-017 Page 3 of 8 for operation at 1775 MWt are approximately 0.05%. This response was augmented by responses provided in L-MT-09-042, dated June 16, 2009, Monticello Extended Power Uprate: Response to NRC Reactor Inspection Branch Request for Additional Information (RAI) dated March 20, 2009 (TAC No.
MD9990), Accession No. ML091671787. This response clarified the impact on turbine gamma shine, or sky shine. Sky shine is predominantly impacted by changes in steam velocity and N-16 concentrations at turbine components. The response to NRC RAI No. 3 in this letter provided more detail on how MCO is evaluated.
The impact of MCO on environmental qualification is provided in Task Report T1 004 which was provided as part of Enclosure 17 of NSPM letter to NRC, License Amendment Request: Extended Power Uprate (L-MT-08-052) dated November 5, 2008 Accession No. ML083230111. The MCO assumptions (see Section 3.3, Item 2 of Task Report T1004), used for environmental qualification are consistent with the information provided in L-MT-08-041 as augmented by L-MT-09-042 described above.
MELLLA + Evaluation NEDC-33435P Rev 1, Safety Analysis Report for Monticello Maximum Extended Load Line Limit Analysis Plus provided information regarding MCO and determined that "the Monticello cycle average value will be monitored and controlled within the existing analytical assumption of 0.5 wt%." This ensures that there will be no change from the values assumed for current operation, i.e.
EPU operation.
The evaluation of steam separator and dryer performance at MELLLA+
conditions indicates an increase in MCO will occur. The effect of increasing steam moisture content has been analyzed and is discussed in the following sections of NEDC-33435P:
- a. 3.5.1.1 Main Steam and Feedwater Piping Inside Containment
- b. 8.1.2 Waste Volumes
- c. 8.4.2 Fission and Activation Corrosion Products
- d. 8.5.1 Normal Operational Radiation Levels
- e. 8.5.2 Post-Shutdown Radiation Levels
- f. 10.4.1 Steam Separator-Dryer Performance
- g. 10. 7.2 Flow Accelerated Corrosion
L-MT-10-017 Page 4 of 8 NRC Acceptance Review RAI 3 Sections 4.1.3 and 4.1.4 of the M+SAR refer to the containment dynamic loads.
Please provide information regarding the plant-specific analyses that were performed to assess the containment dynamic loads. This information should include details regarding the analysis, including: (1) the methods used, (2) assumptions made, and (3) numerical results. Since comparisons are made between MELLLA+ and EPU operation please provide equivalent information for both. For the safety relief valve analysis, please include discussion of postulated, limiting design-basis accident conditions. The discussion should address vessel pressurization under certain loss-of-coolant accident (LOCA) scenarios.
Response
The response to RAI 3 is contained within Attachment 2.
L-MT-10-017 Page 5 of 8 NRC Acceptance Review RAI 4 Section 4.3.5 of the M+SAR discusses the core wide metal water reaction. This section states that the limiting LOCA scenario is calculated to result in 1 percent core wide metal water reaction. This value is equal to the 10 CFR 50.46 acceptance criterion of 1 percent. Since the calculated value is equal to the acceptance criterion, the NRC staff needs more detailed information regarding the [plant-specific LOCA calculations to begin its review.
Response
The response to RAI 4 is contained within Attachment 2.
L-MT-10-017 Page 6 of 8 NRC Acceptance Review RAI Section 5.1.5 of the M+SAR does not fully address Limitation 12.15 from Section 5.1.1.5.3 of the SER for the M+LTR. Provide the operator actions and procedures that will mitigate the impact of the bypass voiding on the TIPs and the core simulator used to monitor the fuel performance. Provide discussion on what impact the bypass voiding greater than 5 percent will have on the neutron monitoring system.
Response
The impact of the bypass voiding, including voiding greater than 5%, on the transversing incore probes (TIPs) and the core simulator used to monitor fuel performance is mitigated by the existing capability of Monticello's GARDEL-BWR core monitor, which uses SIMULATE-3 to explicitly model the impact of local bypass voiding.
The impact of local bypass voiding on both the predicted power distribution and the predicted detector response is modeled by SIMULATE-3 to calculate thermal limit margins adapted to the measured TIP and local power range monitor (LPRM) detector signals. The reduced signals for the TIP and LPRM fission detectors in the presence of bypass voiding are taken into account. No special plant operator actions or procedures are required to address bypass voiding. The core monitor will automatically adjust thermal limits with appropriate penalties for plant operating conditions such as MELLLA+ and single loop operation (SLO).
Monticello's core monitor uncertainty is bounded by the original General Electric thermal analysis basis (GETAB) uncertainty study (NEDO-10958-A).
Monticello's core monitor thermal limits will include the uncertainties and assessments and conform to the limitations and conditions specified in the interim methods licensing topical report (IMLTR) and MELLLA+ LTR NRC SERs.
Any penalties on the critical power ratio (CPR) operating limit that depend on core flow can be specified in the standard input defining the thermal limits for SIMULATE-3.
L-MT-10-017 Page 7 of 8 NRC Acceptance Review RAI 6 Sections 10.9.1 and 10.9.2 discuss the emergency operating procedures (EOPs) and the abnormal operating procedures (AOPs), respectively. Section 10.9 of the staff's SER for the M+LTR states that licensees are expected to indicate any EOP and AOP changes related to MELLLA+ operation in their applications for amendment. Your application states that EOPs and AOPs will be reviewed and revised. Review the EOPs and AOPs, revise as necessary, and provide the revisions as part of the LAR.
Response
In discussions held with the NRC on February 19, 2010, NSPM described to the NRC that procedure revisions are not available at this time. Procedure revisions will be completed after approval of the license amendment request and prior to implementation of MELLLA+. Below is a brief description of the EOP and AOP changes that are planned at this time:
Emergency Operating Procedures(EOPs)
At MELLLA+ operating conditions, the Anticipated Transient Without SCRAM (ATWS) event has the potential to affect EOP actions, and confirmation that the ATWS calculation is consistent with plant-specific operator actions is discussed in Section 12.23.4 of the staff's safety evaluation of the M+ LTR dated October 15, 2008.
Accordingly, NSPM has confirmed that the MELLLA+ ATWS analysis is consistent with the current EPU EOP operator actions and does not require a new EOP operator action or a change to an existing EOP operator action to demonstrate successful event mitigation. In addition, the Heat Capacity Temperature Limit (HCTL), which will be changed to accommodate EPU accident scenarios, will not require additional changes for MELLLA+ operation.
The Monticello Nuclear Generating Plant (MNGP) ATWS analysis does not predict hot shutdown prior to reaching the HCTL. Because of the modeling limitations of the licensing-basis ODYN code with respect to ATWS depressurization and certain EOP actions, a best-estimate TRACG analysis of the limiting ATWS event with depressurization was performed. The TRACG analysis included all plant-specific MNGP EOP actions. The analysis demonstrated that reactor, containment, and fuel integrity acceptance criteria are satisfied at MELLLA+ operating conditions. This approach is in accordance with Section 9.3.1.3 of the staff's safety evaluation of the M+ LTR dated October 15, 2008.
In addition to the ATWS analyses above, a TRACG analysis of the ATWS event with core instability was performed at MELLLA+ operating conditions. This analysis demonstrated that MNGP EOP actions, including boron injection and
L-MT-10-017 Page 8 of 8 water level strategy, will mitigate an ATWS with a core instability event at MELLLA+ operating conditions.
Abnormal OperatingProcedures(AOPs)
NSPM determined that various AOPs are impacted by MELLLA+ and DSS-CD operation. In general, the affected AOPs are those that involve power reductions and/or recirculation pump trips and those that involve actions for mitigation of potential thermal hydraulic instability consistent with the MELLLA+ changes to the Power/Flow Map and DSS-CD implementation.
The AOPs subject to revision identified at this time include the following:
- C.4-B.01.04.A, Trip of One Recirculation Pump
- C.4-B.01.04.B, Trip of Two Recirulation Pumps
- C.4-B.05.01.02.A, Control of Neutron Flux Oscillations
- C.4-F, Rapid Power Reduction
- C.4-K, Immediate Power Reduction In addition, C.4-B.03.03.A, Stuck Open Relief Valve, will be revised to address the effect of a single inoperable safety/relief valve (S/RV) on the ability to limit the predicted peak ATWS pressure.
ATTACHMENT 2 SUPPLEMENTAL INFORMATION NEEDED TO COMPLETE THE ACCEPTANCE REVIEW FOR THE PROPOSED MELLLA+
AMENDMENT, REQUESTS FOR ADDITIONAL INFORMATION 1, 3 AND 4 - GE-MNGP-AEP-1687, Rev. 1, "GEH Responses to NRC Supplemental Requests 1, 3, and 4," GEH Proprietary Information - GE-MNGP-AEP-1687, Rev. 1, "GEH Responses to NRC Supplemental Requests 1, 3, and 4," Non-proprietary - GE-MNGP-AEP-1687, Rev. 1, "Affidavit" 58 pages follow
ENCLOSURE 3 GE-MNGP-AEP-1687, Rev. 1 Affidavit
GE-Hitachi Nuclear Energy Americas LLC AFFIDAVIT I, Edward D. Schrull, state as follows:
(1) I am the Vice President of Regulatory Affairs, Services Licensing, GE-Hitachi Nuclear Energy Americas LLC (GEH), and have been delegated the function of reviewing the information described in paragraph (2) which is sought to be withheld, and have been authorized to apply for its withholding.
(2) The information sought to be withheld is contained in Enclosure 1 of GEH letter, GE-MNGP-AEP-1687, Revision 1, B. Hagemeier, GEH, to A. Williams, Northern States Power
- Minnesota, "GEH Responses to NRC Supplemental Requests 1, 3, and 4," dated March 4, 2010. The proprietary information in Enclosure 1 of that letter, which is entitled, "GEH Responses to NRC Supplemental Requests 1, 3, and 4," is identified by a dotted underline inside double square brackets. ((Thiýs. sentence is an eam*. * .. 3 ]. In each case, the superscript notation 3 refers to Paragraph (3) of this affidavit that provides the basis for the proprietary determination.
(3) In making this application for withholding of proprietary information of which it is the owner or licensee, GEH relies upon the exemption from disclosure set forth in the Freedom of Information Act (FOIA), 5 USC Sec. 552(b)(4), and the Trade Secrets Act, 18 USC Sec.
1905, and NRC regulations 10 CFR 9.17(a)(4), and 2.390(a)(4) for trade secrets (Exemption 4). The material for which exemption from disclosure is here sought also qualifies under the narrower definition of trade secret, within the meanings assigned to those terms for purposes of FOIA Exemption 4 in, respectively, Critical Mass Energy Proiect v. Nuclear Regulatory Commission, 975 F2d 871 (DC Cir. 1992), and Public Citizen Health Research Group v. FDA, 704 F2d 1280 (DC Cir. 1983).
(4) The information sought to be withheld is considered to be proprietary for the reasons set forth in paragraphs (4)a. and (4)b. above. Some examples of categories of information that fit into the definition of proprietary information are:
- a. Information that discloses a process, method, or apparatus, including supporting data and analyses, where prevention of its use by GEH's competitors without license from GEH constitutes a competitive economic advantage over GEH and/or other companies.
- b. Information that, if used by a competitor, would reduce their expenditure of resources or improve their competitive position in the design, manufacture, shipment, installation, assurance of quality, or licensing of a similar product.
- c. Information that reveals aspects of past, present, or future GEH customer-funded development plans and programs, that may include potential products of GEH.
- d. Information that discloses trade secret and/or potentially patentable subject matter for which it may be desirable to obtain patent protection.
Affidavit for GE-MNGP-AEP-1687, R1 Affidavit Page I of 3
(5) To address 10 CFR 2.390(b)(4), the information sought to be withheld is being submitted to, the NRC in confidence. The information is of a sort customarily held in confidence by GEH, and is in fact so held. The information sought to be withheld has, to the best of my knowledge and belief, consistently been held in confidence by GEH, not been disclosed publicly, and not been made available in public sources. All disclosures to third parties, including any required transmittals to the NRC, have been made, or must be made, pursuant to regulatory provisions or proprietary and/or confidentiality agreements that provide for maintaining the information in confidence. The initial designation of this information as proprietary information, and the subsequent steps taken to prevent its unauthorized disclosure are as set forth in the following paragraphs (6) and (7).
(6) Initial approval of proprietary treatment of a document is made by the manager of the originating component, who is the person most likely to be acquainted with the value and sensitivity of the information in relation to industry knowledge, or who is the person most likely to be subject to the terms under which it was licensed to GEH. Access to such documents within GEH is limited to a "need to know" basis.
(7) The procedure for approval of external release of such a document typically requires review by the staff manager, project manager, principal scientist, or other equivalent authority for technical content, competitive effect, and determination of the accuracy of the proprietary designation. Disclosures outside GEH are limited to regulatory bodies, customers, and potential customers, and their agents, suppliers, and licensees, and others with a legitimate need for the information, and then only in accordance with appropriate regulatory provisions or proprietary and/or confidentiality agreements.
(8) The information identified in paragraph (2) above is classified as proprietary because it contains results of an analysis performed by GEH to support Monticello's Maximum Extended Load Line Limit Analysis Plus (MELLLA+) license application. This analysis is part of the GEH MELLLA+ methodology. Development of the MELLLA+ methodology and the supporting analysis techniques and information, and their application to the design, modification, and processes were achieved at a significant cost to GEH. The development of the evaluation methodology along with the interpretation and application of the analytical results is derived from the extensive experience database that constitutes a major GEH asset.
(9) Public disclosure of the information sought to be withheld is likely to cause substantial harm to GEH's competitive position and foreclose or reduce the availability of profit-making opportunities. The information is part of GEH's comprehensive BWR safety and technology base, and its commercial value extends beyond the original development cost.
The value of the technology base goes beyond the extensive physical database and analytical methodology and includes development of the expertise to determine and apply the appropriate evaluation process. In addition, the technology base includes the value derived from providing analyses done with NRC-approved methods.
The research, development, engineering, analytical and NRC review costs comprise a substantial investment of time and money by GEH. The precise value of the expertise to Affidavit for GE-MNGP-AEP- 1687, RI Affidavit Page 2 of 3
devise an evaluation process and apply the correct analytical methodology is difficult to quantify, but it clearly is substantial. GEH's competitive advantage will be lost if its competitors are able to use the results of the GEH experience to normalize or verify their own process or if they are able to claim an equivalent understanding by demonstrating that they can arrive at the same or similar conclusions.
The value of this information to, GEH would be lost if the information were disclosed to the public. Making such information available to competitors without their having been required to undertake a similar expenditure of resources would unfairly provide competitors with a windfall, and deprive GEH of the opportunity to exercise its competitive advantage to seek an adequate return on its large investment in developing and obtaining these very valuable analytical tools.
I declare under penalty of perjury that the foregoing affidavit and the matters stated therein are true and correct to the best of my knowledge, information, and belief.
Executed on this 3rd day of March 2010.
Edward D. Schrull Vice President, Regulatory Affairs Services Licensing GE-Hitachi Nuclear Energy Americas LLC 3901 Castle Hayne Rd.
Wilmington, NC 28401 edward.schrull@ge.com Affidavit for GE-MNGP-AEP-1687, RI Affidavit Page 3 of 3