Letter Sequence Request |
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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 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
MONTHYEARML24283A1192024-10-28028 October 2024 Letter to Shawn Hafen, Re Monticello Subsequent License Renewal Schedule Change L-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 ML24277A0202024-10-0303 October 2024 Operator Licensing Examination Approval Monticello Nuclear Generating Plant, October 2024 ML24199A1752024-10-0101 October 2024 Issuance of Amendment No. 212 Revise Technical Specification 3.8.6, Battery Parameters, Surveillance Requirement 3.8.6.6 IR 05000263/20240112024-10-0101 October 2024 Biennial Problem Identification and Resolution Inspection Report 05000263/2024011 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 IR 05000263/20240052024-08-30030 August 2024 Updated Inspection Plan and Follow-Up Letter for Monticello Nuclear Generating Plant, Unit 1 (Report 05000263/2024005) L-MT-24-028, Response to RCI for RR-017 ISI Impracticality2024-08-28028 August 2024 Response to RCI for RR-017 ISI Impracticality ML24222A1822024-08-27027 August 2024 – Proposed Alternative Request VR-09 to the Inservice Testing Requirements of the ASME OM Code for Main Steam Safety Relief Valves 05000263/LER-2024-002, Low Pressure Coolant Injection Inoperable Due to Motor Valve Failure2024-08-27027 August 2024 Low Pressure Coolant Injection Inoperable Due to Motor Valve Failure IR 05000263/20244202024-08-21021 August 2024 Security Baseline Inspection Report 05000263/2024420 - Cover Letter IR 05000263/20240022024-08-14014 August 2024 Integrated Inspection Report 05000263/2024002 ML24218A2282024-08-0505 August 2024 Request for Confirmation of Information for Relief Request RR-017, Inservice Inspection Impracticality During the Fifth Ten-Year Interval ML24208A1502024-07-26026 July 2024 Independent Spent Fuel Storage Installation - Submittal of Quality Assurance Topical Report (NSPM-1) ML24215A2992024-07-23023 July 2024 Minnesota State Historic Preservation Office Comments on Monticello SLR Draft EIS ML24198A2372024-07-18018 July 2024 Information Request to Support Upcoming Biennial Problem Identification and Resolution (Pi&R) Inspection at Monticello Nuclear Generating Plant L-MT-24-022, – Preparation and Scheduling of Operator Licensing Examinations2024-07-0909 July 2024 – Preparation and Scheduling of Operator Licensing Examinations ML24164A2402024-06-10010 June 2024 Minnesota State Historic Preservation Office- Comments on Draft Monticello SLR Draft EIS 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 ML24137A2792024-06-0303 June 2024 Audit Summary for License Amendment Request to Revise Technical Specification 3.8.6, Battery Parameters, Surveillance Requirement 3.8.6.6 ML24141A1292024-05-22022 May 2024 Northern States Power Company - Use of Encryption Software for Electronic Transmission of Safeguards Information ML24141A1782024-05-20020 May 2024 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection 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 ML24135A1902024-05-14014 May 2024 Submittal of 2023 Annual Radioactive Effluent Release Report IR 05000263/20240102024-05-13013 May 2024 Age-Related Degrading Inspection Report 05000263/2024010 ML24128A0042024-05-0909 May 2024 Letter to Minnesota State Historic Preservation Office- Section 106 Consultation Regarding the Monticello Nuclear Generating Plant Subsequent License Renewal Application ML24127A1472024-05-0909 May 2024 Letter to Mille Lacs Band- Section 106 Consultation Regarding the Monticello Nuclear Generating Plant Subsequent License Renew. Application 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) ML24089A2382024-04-29029 April 2024 Summary of Nuclear Property Insurance IR 05000263/20240012024-04-29029 April 2024 Plan - Integrated Inspection Report 05000263/2024001 ML24115A2902024-04-25025 April 2024 Sec106 Tribal, Jackson-Street, Lonna-Spirit Lake Nation ML24115A2872024-04-25025 April 2024 Sec106 Tribal, Dupuis, Kevin-Fond Du Lac Band of Lake Superior Chippewa ML24115A2932024-04-25025 April 2024 Sec106 Tribal, Johnson, Grant-Prairie Island Indian Community ML24115A3062024-04-25025 April 2024 Sec106 Tribal, Wassana, Reggie-Cheyenne and Arapaho Tribes 05000263/LER-2024-001, Reactor Scram, Containment Isolation, and Cooldown Rate Outside of Limits Following Technician Adjustment of Wrong Component2024-04-25025 April 2024 Reactor Scram, Containment Isolation, and Cooldown Rate Outside of Limits Following Technician Adjustment of Wrong Component ML24115A3032024-04-25025 April 2024 Sec106 Tribal, Taylor, Louis-Lac Courte Oreilles Band of Lake Superior Chippewa Indians ML24115A3002024-04-25025 April 2024 Sec106 Tribal, Rhodd, Timothy-Iowa Tribe of Kansas and Nebraska ML24115A2972024-04-25025 April 2024 Sec106 Tribal, Miller, Cole-Shakopee Mdewakanton Sioux Community ML24115A2962024-04-25025 April 2024 Sec106 Tribal, Larsen, Robert-Lower Sioux Indian Community ML24115A2952024-04-25025 April 2024 Sec106 Tribal, Kakkak, Gena-Menominee Indian Tribe of Wisconsin ML24115A2982024-04-25025 April 2024 Sec106 Tribal, Reider, Anthony-Flandreau Santee Sioux Tribe ML24115A2912024-04-25025 April 2024 Sec106 Tribal, Jacskon, Sr., Faron-Leech Lake Band of Ojibwe ML24115A3052024-04-25025 April 2024 Sec106 Tribal, Vanzile, Jr., Robert-Sokaogon Chippewa Community ML24115A2992024-04-25025 April 2024 Sec106 Tribal, Renville, J. Garret-Sisseton Wahpeton Oyate of the Lake Travers Reservation ML24115A3022024-04-25025 April 2024 Sec106 Tribal, Stiffarm, Jeffrey-Fort Belknap Indian Community ML24115A3072024-04-25025 April 2024 Sec106 Tribal, Williams, Jr., James-Lac Vieux Desert Band of Lake Superior Chippewa Indians ML24115A2892024-04-25025 April 2024 Sec106 Tribal, Fowler, Thomas-St. Croix Chippewa of Wisconsin 2024-09-26
[Table view] Category:Legal-Affidavit
MONTHYEARL-MT-23-030, Subsequent License Renewal Application Supplement 32023-07-0404 July 2023 Subsequent License Renewal Application Supplement 3 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 ML21211A5962021-06-30030 June 2021 Attachments 9a, B, 10a, B, 11a, 12a and 13a and 13b, Including ANP-3933NP, Revision 0, Monticello ATWS-I Evaluation for Atrium 11 Fuel, Affidavit L-MT-21-034, Affidavit for Cycle 31 Core Operating Limits Report - NAD-MN-047P2021-05-13013 May 2021 Affidavit for Cycle 31 Core Operating Limits Report - NAD-MN-047P L-MT-16-028, Transmittal of Extended Power Uprate, Extended Steam Dryer - Response to Requests for Additional Information2016-05-18018 May 2016 Transmittal of Extended Power Uprate, Extended Steam Dryer - Response to Requests for Additional Information ML15289A0732015-10-12012 October 2015 Submittal of Power Ascension Testing Results for Replacement Steam Dryer L-MT-15-065, Enclosure 8, Areva Report ANP-3424NP, Revision 1 to Areva Responses to RAI from Scvb on MNGP EFW LAR (Non-Proprietary) and Enclosure 9, Areva Affidavits2015-09-29029 September 2015 Enclosure 8, Areva Report ANP-3424NP, Revision 1 to Areva Responses to RAI from Scvb on MNGP EFW LAR (Non-Proprietary) and Enclosure 9, Areva Affidavits ML15348A2202015-08-26026 August 2015 Enclosure 9, Areva Affidavits ML14204A7092014-07-23023 July 2014 Enclosure 3, Affidavit of Peter M. Yandow L-MT-14-060, Extended Power Uprate: Replacement Steam Dryer - Response to NRC Requests for Additional Information, Revised Limit Curves and Supporting Information2014-07-22022 July 2014 Extended Power Uprate: Replacement Steam Dryer - Response to NRC Requests for Additional Information, Revised Limit Curves and Supporting Information L-MT-14-016, Calculation 11042-0204, Revision 2, Structural and Allowable Flaw Size Evaluation of the Spent Fuel Storage Canisters with Nonconforming Closure Welds at Monticello Nuclear Generating Plant2014-07-0707 July 2014 Calculation 11042-0204, Revision 2, Structural and Allowable Flaw Size Evaluation of the Spent Fuel Storage Canisters with Nonconforming Closure Welds at Monticello Nuclear Generating Plant ML15348A2152014-07-0707 July 2014 Enclosure 4, General Electric Hitachi (GEH)- Affidavit L-MT-13-126, Enclosure 3, GE-MNGP-AEP-3306, Enclosure 2 GEH Response to Mella+ Eicb RAI and Affidavit2013-12-20020 December 2013 Enclosure 3, GE-MNGP-AEP-3306, Enclosure 2 GEH Response to Mella+ Eicb RAI and Affidavit ML13282A1412013-10-0404 October 2013 Maximum Extended Load Line Limit Analysis Plus License Amendment Request - Request for Additional Information Responses L-MT-13-070, Maximum Extended Load Line Limit Analysis Plus License Amendment Request - Request for Additional Information Responses2013-07-31031 July 2013 Maximum Extended Load Line Limit Analysis Plus License Amendment Request - Request for Additional Information Responses L-MT-13-059, Extended Power Uprate and Maximum Extended Load Line Limit Analysis Plus License Amendment Requests: Response to Request for Additional Information Reactor Systems Branch and Vessel & Internals Integrity Branch and Supplemental Informati2013-06-26026 June 2013 Extended Power Uprate and Maximum Extended Load Line Limit Analysis Plus License Amendment Requests: Response to Request for Additional Information Reactor Systems Branch and Vessel & Internals Integrity Branch and Supplemental Information L-MT-13-033, Extended Power Uprate: Secy 11-0014 Use of Containment Accident Pressure - Responses to Requests for Additional Information2013-03-21021 March 2013 Extended Power Uprate: Secy 11-0014 Use of Containment Accident Pressure - Responses to Requests for Additional Information ML1127000682011-09-26026 September 2011 Enclosure 3, Mfn 10-245 R4, Affidavit ML0923903232009-08-10010 August 2009 Enclosure 2 - Continuum Dynamics Affidavit ML0520003282005-07-14014 July 2005 Surveillance Program for Channel-Control Blade Interference ML0413101222004-04-30030 April 2004 Request for Closed Meeting with USNRC to Discuss NMC Refueling Plans 2023-07-04
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{{#Wiki_filter:ENCLOSURE 1 CONTAINS PROPRIETARY INFORMATIONWITHHOLD FROM PUBLIC DISCLOSURE IN ACCORDANCE WITH 10 CFR 2.390@ XcelEnergyMonticello Nuclear Generating Plant2807 W County Rd 75Monticello, MN 55362July 31, 2013L-MT-13-07010 CFR 50.90U.S. Nuclear Regulatory CommissionATTN: Document Control DeskWashington, DC 20555-0001Monticello Nuclear Generating PlantDocket 50-263Renewed License No. DPR-22Subject: Maximum Extended Load Line Limit Analysis Plus License AmendmentRequest -Request for Additional Information Responses (TAC ME3145)References:1)Letter from T J O'Connor (NSPM), to Document Control Desk (NRC),"License Amendment Request: Maximum Extended Load Line LimitAnalysis Plus," L-MT-10-003, dated January 21, 2010. (ADAMSAccession No. ML100280558)2) Email from T Beltz (NRC) to J Fields (NSPM), "Monticello -MELLLA+ Review -Draft Requests for Additional Information (TACNo. ME3145).docx," dated April 9, 2013.In Reference 1, Northern States Power Company, a Minnesota corporation (NSPM),doing business as Xcel Energy, requested approval of an amendment to the MonticelloNuclear Generating Plant (MNGP) Renewed Operating License (OL) and TechnicalSpecifications (TS). The proposed change would allow operation in the expandedMaximum Extended Load Line Limit Analysis Plus (MELLLA+) domain.In Reference 2 the NRC provided a Request for Additional Information (RAI) pertainingto the quench front velocity in the TRACG model.Enclosure 1 provides a report from General Electric -Hitachi (GEH) letter, GE-MNGP-AEP-3296R2, "GEH Response to RAI-3 Parts a-g and i." Enclosure 1 containsproprietary information.
Document Control DeskPage 2Enclosure 2 provides a non-proprietary copy of the Enclosure 1 RAI responses. Thenon-proprietary copy of the RAI responses is being provided based on the NRC'sexpectation that the submitter of the proprietary information should provide, if possible,a non-proprietary version of the document with brackets showing where the proprietaryinformation has been deleted.Enclosure 3 contains an affidavit executed to support withholding Enclosure 1 frompublic disclosure. Information in Enclosure 1 contains proprietary information asdefined by 10 CFR 2.390. The affidavit sets forth the basis on which the informationmay be withheld from public disclosure by the NRC and addresses with specificity theconsiderations listed in 10 CFR 2.390(b)(4). Accordingly, NSPM respectfully requeststhat the proprietary information in Enclosure 1 be withheld from public disclosure inaccordance with 10 CFR 2.390(a)4, as authorized by 10 CFR 9.17(a)4.Correspondence with respect to the copyright or proprietary aspects of GEH informationor the supporting GEH affidavit in Enclosure 3 should be addressed to James FHarrison, Vice President, Regulatory Affairs, GE-Hitachi Nuclear Energy Americas LLC,3901 Castle Hayne Road, Wilmington, NC 28401.The supplemental information provided herein does not change the conclusions of theNo Significant Hazards Consideration and the Environmental Consideration evaluationsprovided in Reference 1 for the MELLLA+ license amendment request.In accordance with 10 CFR 50.91(b), a copy of this application supplement, withoutenclosures is being provided to the designated Minnesota Official.Summary of CommitmentsThis letter makes no new commitments or revisions to existing commitments.
Document Control DeskPage 3I declare under penalty of perjury that the foregoing is true and correct.Executed on: July ;9, 2013Mark A. SchimmelSite Vice-PresidentMonticello Nuclear Generating PlantNorthern States Power Company-MinnesotaEnclosures (3)cc: Regional Administrator, Region Ill, USNRC (w/o enclosures)Project Manager, Monticello Nuclear Generating Plant, USNRCResident Inspector, Monticello Nuclear Generating Plant, USNRC (w/oenclosures)Minnesota Department of Commerce (w/o enclosures)
L-MT-1 3-070ENCLOSURE 2GE-MNGP-AEP-3296R2, ENCLOSURE 2GEH RESPONSE TO RAI-3 PARTS A-G AND INON-PROPRIETARY9 pages follow ENCLOSURE 2GE-MNGP-AEP-3296R2GEH Response to RAI-3 Parts a-g and iNon-proprietary Information -Class I (Public)NON-PROPRIETARY NOTICEThis is a non-proprietary version of the Enclosure 1 of GE-MNGP-AEP-3296R2 whichhas the proprietary information removed. Portions of the document that have beenremoved are indicated by an open and closed bracket as shown here [[ I].
GE-MNGP-AEP-3296R2 Non-proprietary Information- Class I (Public)Enclosure 2Page 2 of 9RAI-3Detailed Code Questionsa. Please explain how TRACG differentiates between the quench front and the bulk liquidphase in any given node during A TIWS-I conditions when heat is transferred from a hotrod to the liquid downstream of the quench front.ResponseTRACG employs a one-dimensional two-fluid model in each fuel channel. Thereforethere is one void fraction and one liquid temperature for each node. Heat transfer to thebulk liquid does vary between individual surfaces in the node, such as the surfaces forindividual fuel rods, water rods and channel box. Heat transfer to the bulk liquid iscalculated according to the heat transfer selection logic described in Section 6.6.2 of theTRACG Model Description LTR [3-1]. The sum of the heat transfer to the liquid from allthe surfaces in the node is the net heat transfer to the bulk liquid. If a surface in a nodecontains a quench front, the quench front heat transfer is calculated as described inSection 6.6.13 of the TRACG Model LTR [3-1] and discussed in the response to RAI 2 inReference 3-2. The quench front heat transfer is applied to the conduction solution forthe surface containing the quench front, where it becomes an energy loss, and added as asource term to the net heat transfer to the bulk liquid in the node.b. In the response to RAI 2, the first term of Equation 2-2 describes heat transfer accordingtofihn boiling.Please explain how Equation 2-2 accounts for only part of a node being in filn boiling.Response[[
GE-MNGP-AEP-3296R2Enclosure 2Page 3 of 9Non-proprietary Information- Class I (Public)c. The response to RAI 2 states that "For conditions where the energy generation in the fuelis high, the net heat removal given by the difference between Equation 2-2 and the energygeneration rate is reduced and the quenching is similarly slowed down."Please describe by what mechanism is the quench front "slowed downi" in TRA CG?ResponseRAI 2 of Reference 3-2 contains the statement: [[
GE-MNGP-AEP-3296R2Enclosure 2Page 4 of 9Non-proprietary Information- Class I (Public)d. In the response to RAI 2, there is a discussion of Equation 2-3 that notes it is used for"conditions where the energy generation in the fiuel rod is small."Please explain how this expression changes if the energy generation is large, as may bethe case during A TWS conditions.ResponsePlease see the response to RAI 3c above for conditions where the energy generation islarge.
GE-MNGP-AEP-3296R2 Non-proprietary Information- Class I (Public)Enclosure 2Page 5 of 9e. 1) Equation 2-5 relates the quench front heat transfer coefficient to reflood velocitywhich, according to the response to RAI 2, is derived fiom upstream liquid velocity.However, for non-LOCA scenarios such as A TWS-I, the cladding hot spot may be in alow void inverted annular flin boiling (IAFB) regime with oscillatory flow conditions.Please explain how Equation 2-5 is applied to scenarios such as A TWS-I whereupstream liquid velocity may be reversed.ResponseThe quench front models in TRACG were developed for LOCA application.For top down quenching, it is assumed that the quenching is by a falling film. The heattransfer coefficient used in the quench front model for top down quenching is[[ ]] as described in Section 6.6.13 of Reference 3-1.For bottom reflood quenching the heat transfer coefficient used in the quench front modelis the maximum of the above value and Equation 2-5 from Reference 3-2. Equation 2-5from Reference 3-2 has been retained from TRAC-PIA [3-3] and TRAC-BD1 [3-4] andis based on based on Yu, Farmer and Coney [3-5].For conditions with low void fractions and downward velocities, Equation 2-5 fromReference 3-2 is not applied and the falling film quench front model is conservativelyapplied.2) Additionally, the quench fiont propagation would be well correlated with refloodvelocity for oscillatory flow conditions where low void inverted annular flow candevelop.Please provide the basis for Equation 2-5 as applied to this type of situation.ResponseThe basis for the application of Equation 2-5 from Reference 3-2 is described above andis given in Reference 3-5.
GE-MNGP-AEP-3296R2 Non-proprietary Information- Class I (Public)Enclosure 2Page 6 of 93) In the "Monticello Audit slides "presented to the staff during the audit (ADAMSAccession No. ML123400521), the GEH model was compared to oscillatory resultsfrom the Stern Lab tests. However, TRA CG appeared to reduce the clad temperatureand quench much faster than the data in the Stern Lab oscillatoiy dryout tests.Please provide a description about why the reduction in clad temperature and quenchoccur faster in TRACG than in the Stern data occurs.Response GE-MNGP-AEP-3296R2 Non-proprietary Information- Class I (Public)Enclosure 2Page 7 of 9f Equation 6.6-158 in the TRACG Model Description Topical Report is an expression thatprovides the heat transfer coefficient for bottom reflood It is reportedly "based on anempirical correlation developedfor TRAC-P1A based on FLECHT reflood data." TheFLECHT data is referenced as:J.0. Cermak, et al., P WR Full Length Emergency Cooling Heat Transfer(FLECHT) Group I Test Report, WCAP- 7435, Westinghouse ElectricCompany, January 1970.Please provide clarification as to whether this statement is a carryover of thedocumentation for TRA C-P1A?Is the TRACG source code for this equation based on the Yu, Farmer, and Coney data?ResponsePlease see the response to RAI 3.e. Reference 116 in the TRACG Model LTR [3-1] isincorrect; it should be Reference 3-5. This will be corrected in the next revision ofReference 3-1.g. A discussion about Equation 2-5 is included in the response to RAI 2. It is stated that thequench front heat transfer coefficient "is consistent with the observations in Reference 2-9." Reference 2-9 notes that in the evaluation of the Harwell data, the heat transfercoefficient in the vicinity of the advancing quench front was 10O Btu/hr-f!t-F [5.6 x 1IsW/m2-K]. When a reflood velocity of 0.5 in/sec is applied to Equation 2-5, the result is aheat transfer coefficient of]. 6x107 W/m2-KPlease explain the inconsistencies between this result and the observation inReference 2-9.ResponseThere really is no inconsistency. Reference 2-9 (Thompson) of Reference 3-2 is forfalling film rewetting. It shows heat transfer coefficients just behind the quench front onthe order of I05 Btu/ft2-hr-F, which in SI units is 6x105 W/m2-K. TRACG uses a heattransfer coefficient of [[ ]] for the falling film quenching. [[For bottom reflood TRACG uses the model from References 3-4 and 3-5. The model isimplemented as described in the TRAC-BDI Model Description [3-4]:
GE-MNGP-AEP-3296R2Enclosure 2Page 8 of 9Non-proprietary Information- Class I (Public)h = FATq = TO -T, is the difference between the Leidenfrost temperature and the liquidtemperature. In the above expression:Fq = aF(F =4.24.1 04V.113-5)3-6)13-7)(1 + VAT)0.130.4839(1 + vATq)20.346for (1 + vAT2) < 40for (1 + vAT2) > 40(3-8)v, is the liquid velocity.In the latter expression for a as described in Reference 3-4 and implemented withinTRACG ATq = T0 -Te is used. An examination of the original paper by Yu, Farmer andConey [3-5] has revealed that u. should be calculated as:=(+ VeAT2) for (1 + veAT2) 40a= , .. (3-9)for (1+ v AT 2) > 40where AT, = Tsat -Te is the amount of liquid subcooling.
GE-MNGP-AEP-3296R2 Non-proprietary Information- Class I (Public)Enclosure 2Page 9 of 9i. The response to RAI 2 provides Equation 2-2 to describe total heat removal from the fuel.Please describe the distribution of heat transferred to the two phases in TRA CG.ResponsePlease see the response to RAI 3b.References:3-1 GE Nuclear Energy, "TRACG Model Description," NEDE 32176P, Revision 4, January2008.3-2 Response to Monticello Nuclear Generating Plant -Draft Request for Additionalinformation re: MELLLA+ License Amendment Request Review (TAC No. ME3145) -Revision 1, GE-MNGP-AEP-3223, December 14, 2012.3-3 USNRC, "TRAC-P IA: An Advanced Best-Estimate Computer Program for PWR LOCAAnalysis," NUREG/CR-0665, Los Alamos Scientific Laboratory, May 1979.3-4 USNRC, "TRAC-BDI: An Advanced Best-Estimate Computer Program for BoilingReactor Loss-of-Coolant Accident Analysis," NUREG/CR-2178, October 1981.3-5 S. K. W. Yu, P. R. Farmer and M. W. Coney, "Methods and Correlations for the Predictionof Quenching Rates on Hot Surfaces," International Journal of Multiphase Flow, 3, 1977,pp. 415-443.3-6 Presentations from the NRC Audit of Monticello MELLLA+ ATWS/I, October 240" and25th, GE-MNGP-AEP-321 1, October 30, 2012.3-7 T. S. Thompson, "On the Process of Rewetting a Hot Surface by a Falling Liquid Film,"Nuclear Engineering and Design Volume 31, Issue 2, January 1975, pp 234-245.
L-MT-13-070ENCLOSURE 3GENERAL ELECTRIC -HITACHI AFFIDAVIT FORWITHHOLDING PROPRIETARY INFORMATION3 pages follow GE-Hitachi Nuclear Energy Americas LLCAFFIDAVITI, James F. Harrison, state as follows:(1) I am the Vice President Fuel Licensing of GE-Hitachi Nuclear Energy Americas LLC(GEH), and have been delegated the function of reviewing the information described inparagraph (2) which is sought to be withheld, and have been authorized to apply for itswithholding.(2) The information sought to be withheld is contained in Enclosure 1 of GEH letter, GE-MNGP-AEP-3296R2, "GEH Response to MELLLA Plus Requests for AdditionalInformation," dated July 19, 2013. The GEH proprietary information in Enclosure 1, whichis entitled "GEH Response to RAI-3 Parts a-g and i," is identified by a dark red dottedunderline inside double square brackets. This sentence is an .e.x.ample3. In each case,the superscript notation (3) refers to Paragraph (3) of this affidavit that provides the basis forthe proprietary determination.(3) In making this application for withholding of proprietary information of which it is theowner or licensee, GEH relies upon the exemption from disclosure set forth in the Freedomof Information Act (FOIA), 5 U.S.C. Sec. 552(b)(4), and the Trade Secrets Act, 18 U.S.C.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 alsoqualifies under the narrower definition of trade secret, within the meanings assigned tothose terms for purposes of FOIA Exemption 4 in, respectively, Critical Mass EnergyProiect v. Nuclear Regulatory Commission, 975 F.2.d 871 (D.C. Cir. 1992), and PublicCitizen Health Research Group v. FDA, 704 F.2.d 1280 (D.C. Cir. 1983).(4) The information sought to be withheld is considered to be proprietary for the reasons setforth in paragraphs (4)a. and (4)b. Some examples of categories of information that fit intothe definition of proprietary information are:a. Information that discloses a process, method, or apparatus, including supporting dataand analyses, where prevention of its use by GEH's competitors without license fromGEH constitutes a competitive economic advantage over GEH or other companies.b. Information that, if used by a competitor, would reduce their expenditure of resourcesor 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-fundeddevelopment plans and programs, that may include potential products of GEH.d. Information that discloses trade secret or potentially patentable subject matter forwhich it may be desirable to obtain patent protection.Affidavit for GE-MNGP-AEP-3296R2Page I of 3 GE-Hitachi Nuclear Energy Americas LLC(5) To address 10 CFR 2.390(b)(4), the information sought to be withheld is being submitted tothe NRC in confidence. The information is of a sort customarily held in confidence byGEH, and is in fact so held. The information sought to be withheld has, to the best of myknowledge and belief, consistently been held in confidence by GEH, not been disclosedpublicly, 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, pursuantto regulatory provisions or proprietary or confidentiality agreements that provide formaintaining the information in confidence. The initial designation of this information asproprietary information, and the subsequent steps taken to prevent its unauthorizeddisclosure 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 theoriginating component, who is the person most likely to be acquainted with the value andsensitivity of the information in relation to industry knowledge, or who is the person mostlikely to be subject to the terms under which it was licensed to GEH. Access to suchdocuments within GEH is limited to a "need to know" basis.(7) The procedure for approval of external release of such a document typically requires reviewby the staff manager, project manager, principal scientist, or other equivalent authority fortechnical content, competitive effect, and determination of the accuracy of the proprietarydesignation. Disclosures outside GEH are limited to regulatory bodies, customers, andpotential customers, and their agents, suppliers, and licensees, and others with a legitimateneed for the information, and then only in accordance with appropriate regulatoryprovisions or proprietary or confidentiality agreements.(8) The information identified in paragraph (2) above is classified as proprietary because itcontains results of an analysis performed by GEH to support the Monticello MaximumExtended Load Line Limit Analysis Plus (MELLLA+) license application. This analysis ispart of the GEH MELLLA+ methodology. Development of the MELLLA+ methodologyand 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 andapplication of the analytical results is derived from the extensive experience database thatconstitutes a major GEH asset.(9) Public disclosure of the information sought to be withheld is likely to cause substantialharm 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 andtechnology base, and its commercial value extends beyond the original development cost.The value of the technology base goes beyond the extensive physical database andanalytical methodology and includes development of the expertise to determine and applythe appropriate evaluation process. In addition, the technology base includes the valuederived from providing analyses done with NRC-approved methods.Affidavit for GE-MNGP-AEP-3296R2Page 2 of 3 GE-Hitachi Nuclear Energy Americas LLCThe research, development, engineering, analytical and NRC review costs comprise asubstantial investment of time and money by GEH. The precise value of the expertise todevise an evaluation process and apply the correct analytical methodology is difficult toquantify, but it clearly is substantial. GEH's competitive advantage will be lost if itscompetitors are able to use the results of the GEH experience to normalize or verify theirown process or if they are able to claim an equivalent understanding by demonstrating thatthey can arrive at the same or similar conclusions.The value of this information to GEH would be lost if the information were disclosed to thepublic. Making such information available to competitors without their having beenrequired to undertake a similar expenditure of resources would unfairly provide competitorswith a windfall, and deprive GEH of the opportunity to exercise its competitive advantageto seek an adequate return on its large investment in developing and obtaining these veryvaluable analytical tools.I declare under penalty of perjury that the foregoing affidavit and the matters stated therein aretrue and correct to the best of my knowledge, information, and belief.Executed on this 19th day of July, 2013.James F. HarrisonVice President Fuel LicensingGE-Hitachi Nuclear Energy Americas LLC3901 Castle Hayne RdWilmington, NC 28401james.harrison@ge.comAffidavit for GE-MNGP-AEP-3296R2Page 3 of 3
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