Letter Sequence Request |
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TAC:MD9990, Clarify Application of Setpoint Methodology for LSSS Functions (Approved, Closed) |
Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance, Acceptance
- Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement
Administration
- Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance
- Meeting, Meeting, Meeting, Meeting, Meeting, Meeting
Results
Other: L-MT-08-091, Calculation 0801040.301, Steam Dryer Outer Hood Submodel Analysis., L-MT-09-002, Response to NRC Probabilistic Risk Assessment (PRA) Branch Requests for Additional Information (Rais) Dated December 5, 2008, L-MT-09-003, Response to NRC Environmental Branch Requests for Additional Information (Rais) Dated December 18, 2008, L-MT-09-004, Enclosure 1 (Continued) to L-MT-09-004, NSPM Response to Containment & Ventilation Branch RAI Number 2, Copy of MNGP Appr T0406 Data Transmittal Pages 1 of 538 Through Pages 538 of 538, L-MT-09-026, Calculation 0000-0081-6958 MNGP-PRNMS-APRM Calc-2008-NP, Rev. 1, Average Power Range Monitor Selected Prnm Licensing Setpoints - EPU Operation (Numac), L-MT-09-027, Extended Power Uprate: Response to Instrumentation and Controls Branch RAI No. 3 Dated April 6, 2009, L-MT-09-044, Extended Power Uprate: Response to NRC Mechanical and Civil Engineering Review Branch (Emcb) Requests for Additional Information (Rais) Dated March 28, 2009, L-MT-09-049, Drawing C.5-2007, Revision 15, Failure to Scram, L-MT-09-073, Extended Power Uprate: Response to NRC Containment and Ventilation Review Branch (Scvb) Requests for Additional Information (Rais) Dated July 2, 2009 and July 14, 2009, L-MT-09-083, Extended Power Uprate: Limit Curves Requested by the Mechanical and Civil Review Branch (Emcb) Associated with Requests for Additional Information (Rais) Dated March 20, 2009, L-MT-09-088, Extended Power Uprate: Revision to Clarify Text in Enclosures 5 and 7 of L-MT-08-052, L-MT-09-097, Extended Power Uprate: Acknowledgement of NRC Review Delay, L-MT-10-025, Extended Power Uprate (Epu): Response to NRC-NSPM February 25, 2010 Conference Call, L-MT-10-072, Extended Power Uprate: Updates to Docketed Information, L-MT-11-044, Uprate (Epu): Update on EPU Commitments, L-MT-12-056, WCAP-17549-NP, Rev. 0, Monticello Replacement Steam Dryer Structural Evaluation for High-Cycle Acoustic Loads Using ACE, L-MT-12-090, Westinghouse, LTR-A&SA-12-8, Rev. 1, Attachment B, Recommendations for Inspections of the Monticello Replacement Steam Dryer., L-MT-12-114, Drawing C.5-2007, Rev. 17, Failure to Scram, L-MT-13-020, Enclosure 1 - Responses to the Gap Analysis, L-MT-13-029, Enclosure 14 to L-MT-13-029 - WCAP-17716-NP, Revision 0, Benchmarking of the Acoustic Circuit Enhanced Revision 2.0 for the Monticello Steam Dryer Replacement Project., L-MT-13-091, WCAP-17716-NP, Revision 1 - Benchmarking of the Acoustic Circuit Enhanced Revision 2.0 for the Monticello Steam Dryer Replacement Project, Enclosure 14, L-MT-13-092, Extended Power Uprate (Epu): Completion of EPU Commitments, Proposed License Conditions and Revised Power Ascension Test Plan, L-MT-13-096, GE-MNGP-AEP-3304R1, Enclosure 4, NEDC-33435 Corrected Pages, L-MT-13-126, Enclosure 3, GE-MNGP-AEP-3306, Enclosure 2 GEH Response to Mella+ Eicb RAI and Affidavit, L-MT-14-023, Maximum Extended Load Line Limit Analysis Plus: Technical Specification Clarifications, L-MT-15-074, Enclosure 7, WCAP-18604-NP, Revision 0, Monticello EPU Main Steam Line Strain Data Evaluation Report., L-MT-16-017, Revised Commitment to Reconcile Analysis of Bypass Voiding for Transition to Areva Analysis Methodology, L-MT-16-071, Submittal of 2016 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46, ML083230111, ML083400402, ML083500575, ML083570610, ML083590127, ML090710680, ML090710683, ML090710684, ML091120578, ML091140470, ML091410121, ML091410122, ML091410123, ML091410124, ML091760769, ML092290250, ML092810554, ML093160816, ML093220925, ML093220964, ML093620024, ML100280558... further results
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MONTHYEARML0907106832008-02-17017 February 2008 Enclosure 1 (Continued) to L-MT-09-004, NSPM Response to Containment & Ventilation Branch RAI Number 2, Attachment 1-1g Through End of Encl. 1 Project stage: Other ML13064A4352008-03-20020 March 2008 CA-95-075, Main Steam Line High Flow Setpoint, Attachment 4 Project stage: Other ML0914101242008-08-11011 August 2008 Monticello - Calculation CA-08-050, Rev. 0, Instrument Setpoint Calculation - Average Power Range Monitor (APRM) Non-Flow Eiased Prnm Setpoints for Cl Tp and EPU Project stage: Other L-MT-08-091, Calculation 0801040.301, Steam Dryer Outer Hood Submodel Analysis.2008-10-31031 October 2008 Calculation 0801040.301, Steam Dryer Outer Hood Submodel Analysis. Project stage: Other ML0832301122008-10-31031 October 2008 NEDC-33322-NP, Revision 3, Monticello Nuclear Generating Plant, Safety Analysis Report, Constant Pressure Power Uprate. Project stage: Request ML0832301112008-11-0505 November 2008 Monticello Nuclear Generating Plant, License Amendment Request: Extended Power Uprate Project stage: Other ML0832301142008-11-0505 November 2008 Monticello Nuclear Generating Plant, Steam Dryer Dynamic Stress Evaluation. Project stage: Request ML0834003662008-12-0202 December 2008 Extended Power Uprate Acceptance Review Questions on Probabilistic Risk Assessment Issues Project stage: Acceptance Review ML0834004022008-12-0505 December 2008 Extended Power Uprate - Monticello - Request to Supplement the Application in the Probabilistic Risk Assessment Area Project stage: Other ML0835000992008-12-11011 December 2008 Monticello Extended Power Uprate (Usnrc TAC MD9990): Acceptance Review Supplement Regarding Steam Dryer Outer Hood Submodel Analysis Project stage: Supplement ML0835303022008-12-16016 December 2008 Draft Request for Additional Information, Environmental Issues of EPU Application Project stage: Draft RAI ML0936200242008-12-18018 December 2008 Report 0800760.401, Rev. 1, Flaw Evaluation and Vibration Assessment of Existing Monticello Steam Dryer Flaws for Extended Power Uprate. Project stage: Other ML0835005752008-12-18018 December 2008 Letter Finding 11/5/08 Application for Amendment Acceptable for Review Project stage: Other ML0835309982008-12-18018 December 2008 EPU Application - Additional RAI Question Regarding an Environmental Issue Project stage: RAI ML0835310022008-12-18018 December 2008 Proposed Eou Amendment - Revised RAI Re. Containment Analysis Project stage: RAI ML0914101222008-12-18018 December 2008 Monticello - Calculation CA-95-075, Revision 1, Main Steam Line High Flow Setpoint Project stage: Other ML0914101212008-12-19019 December 2008 Monticello - Calculation CA-95-073, Revision 4, Reactor Low Water Level SCRAM Setpoint Project stage: Other ML0835901272009-01-14014 January 2009 Letter Conveying Determination That Enclosure 5 of 11/5/08 Application for EPU Amendment Contains Proprietary Information and Withheld from Public Disclosure Project stage: Other ML0835706102009-01-26026 January 2009 Letter Conveying Determination That Enclosure 11 of 11/5/08 Application for EPU Amendment Contains Proprietary Information and Is Withheld from Public Disclosure Project stage: Other L-MT-09-003, Response to NRC Environmental Branch Requests for Additional Information (Rais) Dated December 18, 20082009-01-29029 January 2009 Response to NRC Environmental Branch Requests for Additional Information (Rais) Dated December 18, 2008 Project stage: Other L-MT-09-005, Revision to Attachment 1 of Enclosure 17 of MNGP License Amendment Request for Extended Power Uprate2009-02-0404 February 2009 Revision to Attachment 1 of Enclosure 17 of MNGP License Amendment Request for Extended Power Uprate Project stage: Request L-MT-09-002, Response to NRC Probabilistic Risk Assessment (PRA) Branch Requests for Additional Information (Rais) Dated December 5, 20082009-02-0404 February 2009 Response to NRC Probabilistic Risk Assessment (PRA) Branch Requests for Additional Information (Rais) Dated December 5, 2008 Project stage: Other ML0904204852009-02-11011 February 2009 Draft RAI from Materials Engineering Re. Proposed Extended Power Uprate Amendment Project stage: Draft RAI ML0907106792009-02-17017 February 2009 Monticello, Response to NRC Containment & Ventilation Branch Request for Additional Information (Rals) Dated December 18, 2008 Project stage: Request ML0907106802009-02-17017 February 2009 Monticello, Enclosure 1 to L-MT-09-004, NSPM Response to Containment & Ventilation Branch RAI Number 1 Dated December 18, 2008, Cover Through Copy of MNGP Appr T0406 Data Transmittal Page 424 of 424 Project stage: Other L-MT-09-004, Enclosure 1 (Continued) to L-MT-09-004, NSPM Response to Containment & Ventilation Branch RAI Number 2, Copy of MNGP Appr T0406 Data Transmittal Pages 1 of 538 Through Pages 538 of 5382009-02-17017 February 2009 Enclosure 1 (Continued) to L-MT-09-004, NSPM Response to Containment & Ventilation Branch RAI Number 2, Copy of MNGP Appr T0406 Data Transmittal Pages 1 of 538 Through Pages 538 of 538 Project stage: Other ML0907106842009-02-17017 February 2009 Enclosures 2 - 4: NSPM Response to Containment & Ventilation Branch RAI Numbers 2, 3 and 4 Dated December 18, 2008 Project stage: Other L-MT-09-018, Response to NRC Steam Generator Tube Integrity & Chemical Engineering Branch Request for Additional Information (RAI) Dated February 11, 20092009-02-24024 February 2009 Response to NRC Steam Generator Tube Integrity & Chemical Engineering Branch Request for Additional Information (RAI) Dated February 11, 2009 Project stage: Request ML0907100912009-03-11011 March 2009 Conveying Draft RAI Questions from the Instrumentation and Controls Branch Regarding the Proposed Extended Power Uprate Amendment Project stage: Draft RAI ML0907200572009-03-12012 March 2009 Conveys Draft RAI Regarding Fire Protection for the Proposed Extended Power Uprate Amendment Project stage: Draft RAI ML0907800062009-03-18018 March 2009 Draft RAI from Probabilistic Risk Assessment Licensing Branch on the Proposed Extended Power Uprate Amendment Project stage: Draft RAI ML0907800042009-03-18018 March 2009 Conveys Draft RAI by the PRA Licensing Branch on the Proposed EPU Amendment Project stage: Draft RAI ML0907809032009-03-19019 March 2009 Conveys Draft RAI Provided by the Containment and Ventilation Branch on the Proposed Extended Power Uprate Amendment Project stage: Draft RAI ML0907809092009-03-19019 March 2009 RAI from the Containment and Ventilation Branch the Proposed Extended Power Uprate Amendment Project stage: RAI L-MT-09-017, Extended Power Uprate: Response to NRC Reactor Systems Branch & Nuclear Performance & Code Review Branch Request for Additional Information (RAI) Dated January 16, 20092009-03-19019 March 2009 Extended Power Uprate: Response to NRC Reactor Systems Branch & Nuclear Performance & Code Review Branch Request for Additional Information (RAI) Dated January 16, 2009 Project stage: Request ML0908200312009-03-20020 March 2009 Draft RAI Re. Health Physics Issues for the Proposed Extended Power Uprate Amendment Project stage: Draft RAI ML0908200992009-03-23023 March 2009 Draft RAI from the Balance of Plant Branch Re the Proposed Amendment on Extended Power Uprate Project stage: Draft RAI ML0908800022009-03-28028 March 2009 Second Portion of Draft RAI from the Mechanical and Civil Engineering Branch Regarding the Proposed Extended Power Uprate Amendment Project stage: Draft RAI ML0908800032009-03-28028 March 2009 Draft RAI from the Electrical Engineering Branch Re. the Proposed Extended Power Uprate Amendment for Monticello Project stage: Draft RAI ML0908800012009-03-29029 March 2009 Additional Draft RAI Questions from the Containment and Ventilation Branch Proposed EPU Amendment for Monticello Project stage: Draft RAI 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-24-006, Subsequent License Renewal Application Annual Update 1 and Supplement 92024-02-29029 February 2024 Subsequent License Renewal Application Annual Update 1 and Supplement 9 L-MT-24-007, Response to NRC Request for Additional Information on Proposed Inservice Inspection Alternative RR-002 for the Sixth Ten-Year ISI Interval2024-02-15015 February 2024 Response to NRC Request for Additional Information on Proposed Inservice Inspection Alternative RR-002 for the Sixth Ten-Year ISI Interval L-MT-24-001, 10 CFR 50.55a Request RR-017 - Inservice Inspection (ISI) Impracticality in Accordance with 10 CFR 50.55a(g)(5)(iii) During the Fifth Ten-Year Interval2024-01-30030 January 2024 10 CFR 50.55a Request RR-017 - Inservice Inspection (ISI) Impracticality in Accordance with 10 CFR 50.55a(g)(5)(iii) During the Fifth Ten-Year Interval L-MT-23-054, Subsequent License Renewal Application Supplement 82024-01-11011 January 2024 Subsequent License Renewal Application Supplement 8 L-MT-23-047, License Amendment Request: Revision to the MNGP Pressure Temperature Limits Report to Change the Neutron Fluence Methodology and Incorporate New Surveillance Capsule Data2023-12-29029 December 2023 License Amendment Request: Revision to the MNGP Pressure Temperature Limits Report to Change the Neutron Fluence Methodology and Incorporate New Surveillance Capsule Data L-MT-23-056, Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 1 Part 22023-12-18018 December 2023 Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 1 Part 2 L-MT-23-042, 2023 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.462023-12-11011 December 2023 2023 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46 L-MT-23-052, Subsequent License Renewal Application Supplement 72023-11-30030 November 2023 Subsequent License Renewal Application Supplement 7 L-MT-23-051, Update to the Technical Specification Bases2023-11-28028 November 2023 Update to the Technical Specification Bases L-MT-23-049, Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 12023-11-21021 November 2023 Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 1 L-MT-23-043, 10 CFR 50.55a(z)(1) Request Regarding OMN-17, Revision 1. VR-092023-11-13013 November 2023 10 CFR 50.55a(z)(1) Request Regarding OMN-17, Revision 1. VR-09 L-MT-23-038, License Amendment Request to Revise Monticello Technical Specification Surveillance Requirement 3.8.6.62023-11-10010 November 2023 License Amendment Request to Revise Monticello Technical Specification Surveillance Requirement 3.8.6.6 L-MT-23-046, Subsequent License Renewal Application Response to Request for Additional Information Round 2 - Set 12023-11-0909 November 2023 Subsequent License Renewal Application Response to Request for Additional Information Round 2 - Set 1 L-MT-23-041, Subsequent License Renewal Application Response to Request for Confirmation of Information Set 22023-10-0303 October 2023 Subsequent License Renewal Application Response to Request for Confirmation of Information Set 2 L-MT-23-037, Subsequent License Renewal Application Response to Request for Additional Information Set 32023-09-22022 September 2023 Subsequent License Renewal Application Response to Request for Additional Information Set 3 L-MT-23-036, Subsequent License Renewal Application Response to Request for Additional Information Set 2 and Supplement 62023-09-0505 September 2023 Subsequent License Renewal Application Response to Request for Additional Information Set 2 and Supplement 6 L-MT-23-035, Subsequent License Renewal Application Supplement 52023-08-28028 August 2023 Subsequent License Renewal Application Supplement 5 L-MT-23-034, Subsequent License Renewal Application Response to Request for Additional Information Set 12023-08-15015 August 2023 Subsequent License Renewal Application Response to Request for Additional Information Set 1 L-MT-23-032, 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-23-028, 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-23-031, 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) 2024-07-09
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WITHHOLD ENCLOSURE 3 FROM PUBLIC DISCLOSURE UNDER 10 CFR 2.390 and 9.19 April 22, 2009 L-MT-09-025 10 CFR 50.90 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Monticello Nuclear Generating Plant Docket 50-263 Renewed Facility Operating License License No. DPR-22 Monticello Extended Power Uprate: Response to NRC Reactor Systems Branch and Nuclear Performance & Code Review Branch Request for Additional Information ( M I )
dated Februaw 23,2009 (TAC No. MD9990)
References:
I. NSPM letter to NRC, License Amendment Request: Extended Power Uprate (L-MT-08-052) dated November 5, 2008 (TAC No. MD9990)
Accession No. ML083230111
- 2. Email P. Tam (NRC) to G. Salamon, K. Pointer (NSPM) dated February 23, 2009, Monticello - Second portion of draft RAl on reactor systems for proposed EPU amendment (TAC MD9990)
Pursuant to 10 CFR 50.90, the Northern States Power Company, a Minnesota corporation (NSPM), requested in Reference Ian amendment to the Monticello Nuclear Generating Plant (MNGP) Renewed Operating License (OL) and Technical Specifications (TS) to increase the maximum authorized power level from 1775 megawatts thermal (MWt) to 2004 MWt.
The U. S. Nuclear Regulatory Commission (NRC) Reactor Systems Branch initially provided six RAls as described in Reference 2. RAI 2.8.5.6-6 was withdrawn during a subsequent conference call on March 11, 2009. Enclosure 1 provides the non-proprietary version of the NSPM response. The proprietary version of the NSPM response is provided as Enclosure 3.
This enclosure contains information which is proprietary to GE Hitachi (GEH). GEH requests this proprietary information be withheld from public disclosure in accordance with 10 CFR 2.390(a)4 and 9.17(a)4. An affidavit supporting this request is provided in Enclosure 2.
Document Control Desk Page 2 of 2 GEH, as the owner of the proprietary information, has executed the enclosed affidavit, which identifies that the enclosed proprietary information has been handled and classified as proprietary, is customarily held in confidence, and has been withheld from public disclosure.
In accordance with 10 CFR 50.91, a copy of this letter without the proprietary enclosure is being provided to the designated Minnesota Official.
Summary of Commitments There are no new commitments contained in this letter and no existing commitments revised by this letter.
I declare under penalty of perjury that the foregoing is true and correct.
Executpd on April &2, 2009.
President, Monticello Nuclear Generating Plant States Power Company - Minnesota Enclosures (3) cc: Administrator, Region Ill, USNRC Project Manager, Monticello, USNRC Resident Inspector, Monticello, USNRC Minnesota Department of Commerce (wlo proprietary Enclosure 3)
ENCLOSURE I NSPM RESPONSE TO REACTOR SYSTEMS BRANCH RAls DATED FEBRUARY 23,2009 (Non-Proprietary)
L-MT-09-025 Page 1 of 11 NRC RAI 2.8.5.6-1 As published in Rev. 24 of the MNGP FSAR, the Licensing Basis PCT for the large-.
break LOCA evaluation is 1975F. The PUSAR states, on Page 2-294, ((
I] While this conclusion may be true, it suggests that analytic model changes have been made that affect the LBPCT separate from the plant changes necessary to implement the requested uprate. Please compare all differences in the LOCA model considering ( I ) the current licensing basis, (2) the CLTP case evaluated and described in the PUSAR, and (3) the EPU case evaluated in the PUSAR. Please provide the comparison in tabular format.
NSPM Response Table 2.8.5.6-1 provides the key differences in the LOCA model when comparing ( I )
the current licensing basis, (2) the CLTP case evaluated in the PUSAR, and (3) the EPU'case evaluated in the PUSAR. (Note, the cases listed in Table 2.8.5.6-1 reflected the limiting Appendix K cases).
Table 2.8.5.6-1
L-MT-09-025 Enclosure I Page 2 of 11 Licensing Basis PCT < 1970" * < 2140 < 2140 (OF) (< 1990, Ref. 2)
- Talcen from Reference 1 unless notes in parenthesis.
- Shown is the LBPCT from the current DBA analysis basis (Ref. 1). The PCT of 1975°F referred in the RAI text accounts for changes in PCT annotated in 10CFR50.46 annual report (Ref. 3).
L-MT-09-025 Page 3 of 11
L-MT-09-025 Page 4 of 11 References 2.8.5.6-1 -1. GE-NE-J1103878-09-02P, Monticello ECCS-LOCA Evaluation for GE14, August 2001.
2.8.5.6-1-2. GE-NE-0000-0052-3113-P-RO, Monticello Nuclear Generating Plant SAFEWGESTR ECCS-LOCA Analysis - LPCl Loop Selection Detectable Break Area, September 2006.
2.8.5.6-1-3. 2006 Report of Changes and Errors in ECCS Evaluation Models, December 30,2006.
2.8.5.6-1-4. General Electric B WR Licensing Report: Average Power Range Monitor, Rod Block Monitor and Technical Specification Improvement (ARTS) Program for Monticello Nuclear Generating Plant, NEDC-30492-P, April 1984.
L-MT-09-025 Page 5 of 11 NRC RAI 2.8.5.6-2 The generic disposition for EPU LOCA relies on the fact that the break spectrum response is determined by the ECCS network design and is common to all BWRs.
However, a license amendment request currently under staff review for MNGP provides LOCA analysis results that challenge this assertion. Licensing basis PCTs in the concurrent request are higher for different break sizes and locations than for the break size and location set forth in the generic disposition. In light of this information, please justify the generic disposition, accounting for the changes requested in the concurrent license amendment request and how they impact the break spectrum response, and how those changes are affected by EPU implementation.
NSPM Response The change for minimum detectable break area of LPCl Loop Select (Ref. 2.8.5.6 2) was recently approved by the NRC for MNGP.
The EPU new analysis was performed based on the changes described in Table 2.8.5.6-1. ((
I]. The limiting break location and limiting single failure is discussed in the response to RAI 2.8.5.6-3.
The EPU LOCA analysis has confirmed the break spectrum response. A large break analysis was performed at various break area sizes ((
I] The small breaks and large break presented in the PUSAR are the limiting breaks.
L-MT-09-025 Enclosure I Page 6 of 11 Reference 2.8.5.6-2-1. NEDE-23785P-A, Vol. I l l , Supplement 1 , Revision I , GESTR-LOCA and SAFER Models for Evaluation of Loss-of-Coolant Accident Volume 111, Supplement I, Additional Information for Upper Bound PCT Calculation, March 2002.
2.8.5.6-2-2. G E-N E-0000-0052-3113-P-RO, Monticello Nuclear Generating Plant SAFEWGESTR ECCS-LOCA Analysis - LPCl Loop Selection Detectable Break Area, September 2006.
L-MT-09-025 Page7of 11 NRC RBI 2.8.5.6-3 The PUSAR states, "The Appendix K results confirm that the limiting break is the recirculation suction line DBA and that the LPCl injection valve failure is the limiting single failure." Subsequent sentences suggest that analyses were performed at different statepoints to establish the limiting PCT for the limiting break and single failure identified above.
- a. Please confirm whether the Appendix K evaluations discussed in this paragraph (spanning pages 2-295 and 2-296 of the PUSAR) all employed the same break and single failure.
- b. Provide additional information to describe how the statement quoted above is confirmed.
NSPM Response Response to Part a Confirmed.
Response to Part b For the generalized modeling in SAFER, ((
I] and the DBA is confirmed to be the limiting large break for Monticello.
This result is consistent with the GE14 New Fuel Introduction conclusions (Ref.
2:8.5.6-3-1).
Ref. 2.8.5.6-3-lalso shows the PCT results for the different single failure analysis.
[E .
I] The changes described in response to RAI 2.8.5.6-2 do
L-MT-09-025 Page 8 of 11 not impact the relative severity of the single failure to a degree that would change this conclusion.
Reference 2.8.5.6-3-1 . GE-N E-J I I 03878-09-02P, Monticello ECCS-LOCA Evaluation for GE14, August 2001.
2.8.5.6-3-2. NEDC-33004P-A, Licensing Tbpical Report Constant Pressure Power Uprate, Rev. 4 , July 2003.'
L-MT-09-025 Page 9 of 11 NRC RAI 2.8.5.6-4 The PUSAR states that the increased decay heat associated with EPU results in a longer ADS blowdown and a higher PCT for the small break LOCA. A license amendment request currently under staff review presents small break LOCA results with higher PCT than the EPU small break LOCA results. please explain.
NSPM Response The EPU small break analysis was performed based on ((
Reference:
2.8.5.6-4-1. GE-NE-0000-0052-3113-P-RO, Monticello Nuclear Generating Plant SAFEWGESTR ECCS-LOCA Analysis - LPCl Loop Selection Detectable Break Area, September 2006.
L-MT-09-025 Enclosure I Page 10 of 11 NRC RAI 2.8.5.6-5 The PUSAR states, "plant specific analyses demonstrate that there is sufficient ADS capacity at EPU conditions with all ADS valves available. With two ADS valves available, an LHGR multiplier is applied to ensure that the small break is not limiting." Please clarify whether this constitutes a conservative analytic assumption, or an operating restriction employed at the plant when operating with h o ADS valves available.
NSPM Response The ECCS-LOCA analysis performed for EPU assumed all three ADS valves available and applied the single failure criterion from that point (Table 2.8.5.6-1).
Using this assumption, the EPU analysis does not include an ADS valve inoperable in combination with any other ECCS component. An additional analysis was also provided for the plant to support the potential for operation with two ADS'valves available. An extra LHGR multiplier would be required to reduce the peak power profile so that all of the 10CFR50.46 criteria are still satisfied and without the small break being limiting. This would require a license amendment for implementation, which is not being pursued coincident with EPU.
Although unrelated to this RAI, Section 2.8.5.6.2, subsection, Emergency Core Cooling System Performance, states that a SLO multiplier is applied to both the LHGR and MAPLHGR. However, Monticello applies the multiplier to MAPLHGR only.
A revision to PUSAR page 2-296 is attached which clarifies the application of the SLO multiplier.
L-MT-09-025 Page 11 of 11 failure is the limiting single failure. ((
I] For both EPU and CLTP, the GE14 Licensing Basis PCT is 2140°F and is based on the operating conditions at CLTP power and MELLLA core flow.
The results of these analyses are provided in Table 2.8-5.
In addition to the large break LOCA analysis, the small break LOCA response was reviewed in order to assure adequate ADS capacity. The increased decay heat associated with EPU results in a longer ADS blowdown and a higher PCT for the small break LOCA. Plant specific analyses demonstrate that there is sufficient ADS capacity at EPU conditions with all ADS valves available. With two ADS valves available, a LHGR multiplier is applied to ensure that the small break is not 1-imiting. Also, the plant performance improvement of three SRVs OOS remains valid with EPU.
For SLO, a multiplier is applied to the Two-Loop T U r - D L H G R Operation limits.
The operating conditions for SLO are not changed with EPU; therefore, the current SLO 1
analysis remains acceptable for EPU.
ARTS limits are unaffected by EPU. Also, the effect of ICF on PCT is negligible with EPU.
Thus the ARTS limits, as well as the ICF domain, remain valid with EPU.
Conclusion NSPM has evaluated the LOCA events and the ECCS. The evaluation concludes that operation of the plant at the proposed power level is acceptable In addition, NSPM will perform cycle specific reload analyses to confirm that the peak cladding temperature, total oxidation of the cladding, total hydrogen generation, and changes in core geometry and long-term cooling will remain within acceptable limits. Based on this, the evaluation concludes that the plant will continue to meet the requirements of the current licensing basis and 10 CFR 50.46 following implementation of the proposed EPU, and is, therefore, acceptable.
ENCLOSURE 2 GE Hitachi Affidavit (3 pages follow)
GE-Ritachi Nuclear Energy Americas ELC AFFIDAVIT I, James F. Harrison, state as follows:
(1) I am Vice President, Fuels Licensing, Regulatory Affairs, GE~HitachiNuclear Energy Americas LLC ("GEH"), and have been delegated the function of reviewing the information desclibed in paragraph (2) which is sought to be withheld, and have been authorized to apply for its withholding.
(2) The infomation sought to be withheld is contained in GEH letter, GE-MNGP-AEP-1230, GEH Responses to NRC RAIs 2.8.5.6-1 thru 5, dated April 14, 2009. The proprietary information in Enclosure 1 entitled, GEH Responses to NRC M I S 2.8.5,6-1 thru 5, is identified by a dotted underline inside double square brackets, ((~~.~q..,qg~~g~~gg,,,ii~SS .tg, E?camg!s,.~~!)). In each case, the superscript notation (3) refers to Paragraph (3) of this affidavit, which 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 disclosuse 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 quallfy 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 Project v. Nuclear Regulatory Commission, 975F2d871 (DC Cir. 1992), and Public Citizen Health Research Group v. FDA, 704F2d1280 (DC Cir. 1983).
(4) Some exaniples of categories of information which fit into the definition of proprietary information are:
- a. Information that discloses a process, method, or apparatus, including s-clppol-ting data and analyses, where prevention of its use by GEH's competitors without license from GEH constitutes a competitive economic advantage over other companies;
- b. Information which, if used by a competitor, would reduce his expenditure of resources or improve his competitive position in the design, manufacture, shipment, installation, assurance of quality, or licensing of a'similar product;
- c. Information which reveals aspects of past, present, or future GEH customer-funded developn~entplans and programs, resulting in potential products to GEH;
- d. Information which discloses patentable subject matter for which it may be desirable to obtain patent protection.
Affidavit for MNGP-AEP-1230 Affidavit Page 1 of 3
The infomation Sought to be withheld is considered to be proprietary for the reasons set forth in paragraphs (4)a. and (4)b. above.
(5) To address 10 CFR 2.390(b)(4), the information sought to be withheld is being submitted to NRC in confidence. The infosmation is of a sort customarily held in confidence by GEH, and is in fact so held. The infosmation sought to be withheld has, to the best of my lcnowledge and belief, consistently been held in confidence by GEH, no public disclosure has been made, and it is not available in public sources. All disclosures to third parties, including any required transmittals to NRC, have been made, or must be made, pursuant to regulatory provisions or proprietary agreements which provide for maintenance of the information in confidence. Its initial designation as proprietary information, and the subsequent steps taken to prevent its unauthorized disclosure, are as set forth in paragraphs (6) and (7) following.
(6) Initial approval of proprietary treatment of a document is made by the manager of the originating component, the person most likely to be acquainted with the value and sensitivity of the information in relation to industry lcnowledge, or subject to the terms under which it was licensed to GEH. Access to such documents within GEH is limited on 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 eEect, 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 agseements.
(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 Extended Power Uprate license application. This analysis is part of the GEH Extended Power Uprate methodology. Development of the extended power uprate methodology and the suppoi.ting 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) P~lblicdisclosure of the infoimation sought to be withheld is lilcely to'cause substantial harm to GEH's competitive position and foreclose or reduce the availability of profit-malung oppo~%~nities, 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 Affidavit for MNGP-AEP-1230 Affidavit Page 2 of 3
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 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 GEI-I experience to no~malizeor verify their o w 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 havi,ng 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 seelc an adequate return on its large investment in developing and obtaining these very valuable analytical tools.
I declare under penalty of perjwy that the foregoing affidavit and the matters stated therein are ti-ue and correct to the best of my knowledge, information, and belief.
Executed on this 1 4 ' ~day of April 2009.
James F. Harrison Vice President, Fuels Licensing GE-Hitachi Nuclear Energy Americas LLC Affidavit for MNGP-AEP-1230 Affidavit Page 3 of 3