Letter Sequence Other |
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TAC:MD9990, Clarify Application of Setpoint Methodology for LSSS Functions (Approved, Closed) |
Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance, Acceptance
- Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement
Administration
- Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance
- Meeting, Meeting, Meeting, Meeting, Meeting, Meeting
Results
Other: L-MT-08-091, Calculation 0801040.301, Steam Dryer Outer Hood Submodel Analysis., L-MT-09-002, Response to NRC Probabilistic Risk Assessment (PRA) Branch Requests for Additional Information (Rais) Dated December 5, 2008, L-MT-09-003, Response to NRC Environmental Branch Requests for Additional Information (Rais) Dated December 18, 2008, L-MT-09-004, Enclosure 1 (Continued) to L-MT-09-004, NSPM Response to Containment & Ventilation Branch RAI Number 2, Copy of MNGP Appr T0406 Data Transmittal Pages 1 of 538 Through Pages 538 of 538, L-MT-09-026, Calculation 0000-0081-6958 MNGP-PRNMS-APRM Calc-2008-NP, Rev. 1, Average Power Range Monitor Selected Prnm Licensing Setpoints - EPU Operation (Numac), L-MT-09-027, Extended Power Uprate: Response to Instrumentation and Controls Branch RAI No. 3 Dated April 6, 2009, L-MT-09-044, Extended Power Uprate: Response to NRC Mechanical and Civil Engineering Review Branch (Emcb) Requests for Additional Information (Rais) Dated March 28, 2009, L-MT-09-049, Drawing C.5-2007, Revision 15, Failure to Scram, L-MT-09-073, Extended Power Uprate: Response to NRC Containment and Ventilation Review Branch (Scvb) Requests for Additional Information (Rais) Dated July 2, 2009 and July 14, 2009, L-MT-09-083, Extended Power Uprate: Limit Curves Requested by the Mechanical and Civil Review Branch (Emcb) Associated with Requests for Additional Information (Rais) Dated March 20, 2009, L-MT-09-088, Extended Power Uprate: Revision to Clarify Text in Enclosures 5 and 7 of L-MT-08-052, L-MT-09-097, Extended Power Uprate: Acknowledgement of NRC Review Delay, L-MT-10-025, Extended Power Uprate (Epu): Response to NRC-NSPM February 25, 2010 Conference Call, L-MT-10-072, Extended Power Uprate: Updates to Docketed Information, L-MT-11-044, Uprate (Epu): Update on EPU Commitments, L-MT-12-056, WCAP-17549-NP, Rev. 0, Monticello Replacement Steam Dryer Structural Evaluation for High-Cycle Acoustic Loads Using ACE, L-MT-12-090, Westinghouse, LTR-A&SA-12-8, Rev. 1, Attachment B, Recommendations for Inspections of the Monticello Replacement Steam Dryer., L-MT-12-114, Drawing C.5-2007, Rev. 17, Failure to Scram, L-MT-13-020, Enclosure 1 - Responses to the Gap Analysis, L-MT-13-029, Enclosure 14 to L-MT-13-029 - WCAP-17716-NP, Revision 0, Benchmarking of the Acoustic Circuit Enhanced Revision 2.0 for the Monticello Steam Dryer Replacement Project., L-MT-13-091, WCAP-17716-NP, Revision 1 - Benchmarking of the Acoustic Circuit Enhanced Revision 2.0 for the Monticello Steam Dryer Replacement Project, Enclosure 14, L-MT-13-092, Extended Power Uprate (Epu): Completion of EPU Commitments, Proposed License Conditions and Revised Power Ascension Test Plan, L-MT-13-096, GE-MNGP-AEP-3304R1, Enclosure 4, NEDC-33435 Corrected Pages, L-MT-13-126, Enclosure 3, GE-MNGP-AEP-3306, Enclosure 2 GEH Response to Mella+ Eicb RAI and Affidavit, L-MT-14-023, Maximum Extended Load Line Limit Analysis Plus: Technical Specification Clarifications, L-MT-15-074, Enclosure 7, WCAP-18604-NP, Revision 0, Monticello EPU Main Steam Line Strain Data Evaluation Report., L-MT-16-017, Revised Commitment to Reconcile Analysis of Bypass Voiding for Transition to Areva Analysis Methodology, L-MT-16-071, Submittal of 2016 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46, ML083230111, ML083400402, ML083500575, ML083570610, ML083590127, ML090710680, ML090710683, ML090710684, ML091120578, ML091140470, ML091410121, ML091410122, ML091410123, ML091410124, ML091760769, ML092290250, ML092810554, ML093160816, ML093220925, ML093220964, ML093620024, ML100280558... further results
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MONTHYEARML0907106832008-02-17017 February 2008 Enclosure 1 (Continued) to L-MT-09-004, NSPM Response to Containment & Ventilation Branch RAI Number 2, Attachment 1-1g Through End of Encl. 1 Project stage: Other ML13064A4352008-03-20020 March 2008 CA-95-075, Main Steam Line High Flow Setpoint, Attachment 4 Project stage: Other ML0914101242008-08-11011 August 2008 Monticello - Calculation CA-08-050, Rev. 0, Instrument Setpoint Calculation - Average Power Range Monitor (APRM) Non-Flow Eiased Prnm Setpoints for Cl Tp and EPU Project stage: Other L-MT-08-091, Calculation 0801040.301, Steam Dryer Outer Hood Submodel Analysis.2008-10-31031 October 2008 Calculation 0801040.301, Steam Dryer Outer Hood Submodel Analysis. Project stage: Other ML0832301122008-10-31031 October 2008 NEDC-33322-NP, Revision 3, Monticello Nuclear Generating Plant, Safety Analysis Report, Constant Pressure Power Uprate. Project stage: Request ML0832301112008-11-0505 November 2008 Monticello Nuclear Generating Plant, License Amendment Request: Extended Power Uprate Project stage: Other ML0832301142008-11-0505 November 2008 Monticello Nuclear Generating Plant, Steam Dryer Dynamic Stress Evaluation. Project stage: Request ML0834003662008-12-0202 December 2008 Extended Power Uprate Acceptance Review Questions on Probabilistic Risk Assessment Issues Project stage: Acceptance Review ML0834004022008-12-0505 December 2008 Extended Power Uprate - Monticello - Request to Supplement the Application in the Probabilistic Risk Assessment Area Project stage: Other ML0835000992008-12-11011 December 2008 Monticello Extended Power Uprate (Usnrc TAC MD9990): Acceptance Review Supplement Regarding Steam Dryer Outer Hood Submodel Analysis Project stage: Supplement ML0835303022008-12-16016 December 2008 Draft Request for Additional Information, Environmental Issues of EPU Application Project stage: Draft RAI ML0936200242008-12-18018 December 2008 Report 0800760.401, Rev. 1, Flaw Evaluation and Vibration Assessment of Existing Monticello Steam Dryer Flaws for Extended Power Uprate. Project stage: Other ML0835005752008-12-18018 December 2008 Letter Finding 11/5/08 Application for Amendment Acceptable for Review Project stage: Other ML0835309982008-12-18018 December 2008 EPU Application - Additional RAI Question Regarding an Environmental Issue Project stage: RAI ML0835310022008-12-18018 December 2008 Proposed Eou Amendment - Revised RAI Re. Containment Analysis Project stage: RAI ML0914101222008-12-18018 December 2008 Monticello - Calculation CA-95-075, Revision 1, Main Steam Line High Flow Setpoint Project stage: Other ML0914101212008-12-19019 December 2008 Monticello - Calculation CA-95-073, Revision 4, Reactor Low Water Level SCRAM Setpoint Project stage: Other ML0835901272009-01-14014 January 2009 Letter Conveying Determination That Enclosure 5 of 11/5/08 Application for EPU Amendment Contains Proprietary Information and Withheld from Public Disclosure Project stage: Other ML0835706102009-01-26026 January 2009 Letter Conveying Determination That Enclosure 11 of 11/5/08 Application for EPU Amendment Contains Proprietary Information and Is Withheld from Public Disclosure Project stage: Other L-MT-09-003, Response to NRC Environmental Branch Requests for Additional Information (Rais) Dated December 18, 20082009-01-29029 January 2009 Response to NRC Environmental Branch Requests for Additional Information (Rais) Dated December 18, 2008 Project stage: Other L-MT-09-005, Revision to Attachment 1 of Enclosure 17 of MNGP License Amendment Request for Extended Power Uprate2009-02-0404 February 2009 Revision to Attachment 1 of Enclosure 17 of MNGP License Amendment Request for Extended Power Uprate Project stage: Request L-MT-09-002, Response to NRC Probabilistic Risk Assessment (PRA) Branch Requests for Additional Information (Rais) Dated December 5, 20082009-02-0404 February 2009 Response to NRC Probabilistic Risk Assessment (PRA) Branch Requests for Additional Information (Rais) Dated December 5, 2008 Project stage: Other ML0904204852009-02-11011 February 2009 Draft RAI from Materials Engineering Re. Proposed Extended Power Uprate Amendment Project stage: Draft RAI ML0907106792009-02-17017 February 2009 Monticello, Response to NRC Containment & Ventilation Branch Request for Additional Information (Rals) Dated December 18, 2008 Project stage: Request ML0907106802009-02-17017 February 2009 Monticello, Enclosure 1 to L-MT-09-004, NSPM Response to Containment & Ventilation Branch RAI Number 1 Dated December 18, 2008, Cover Through Copy of MNGP Appr T0406 Data Transmittal Page 424 of 424 Project stage: Other L-MT-09-004, Enclosure 1 (Continued) to L-MT-09-004, NSPM Response to Containment & Ventilation Branch RAI Number 2, Copy of MNGP Appr T0406 Data Transmittal Pages 1 of 538 Through Pages 538 of 5382009-02-17017 February 2009 Enclosure 1 (Continued) to L-MT-09-004, NSPM Response to Containment & Ventilation Branch RAI Number 2, Copy of MNGP Appr T0406 Data Transmittal Pages 1 of 538 Through Pages 538 of 538 Project stage: Other ML0907106842009-02-17017 February 2009 Enclosures 2 - 4: NSPM Response to Containment & Ventilation Branch RAI Numbers 2, 3 and 4 Dated December 18, 2008 Project stage: Other L-MT-09-018, Response to NRC Steam Generator Tube Integrity & Chemical Engineering Branch Request for Additional Information (RAI) Dated February 11, 20092009-02-24024 February 2009 Response to NRC Steam Generator Tube Integrity & Chemical Engineering Branch Request for Additional Information (RAI) Dated February 11, 2009 Project stage: Request ML0907100912009-03-11011 March 2009 Conveying Draft RAI Questions from the Instrumentation and Controls Branch Regarding the Proposed Extended Power Uprate Amendment Project stage: Draft RAI ML0907200572009-03-12012 March 2009 Conveys Draft RAI Regarding Fire Protection for the Proposed Extended Power Uprate Amendment Project stage: Draft RAI ML0907800062009-03-18018 March 2009 Draft RAI from Probabilistic Risk Assessment Licensing Branch on the Proposed Extended Power Uprate Amendment Project stage: Draft RAI ML0907800042009-03-18018 March 2009 Conveys Draft RAI by the PRA Licensing Branch on the Proposed EPU Amendment Project stage: Draft RAI ML0907809032009-03-19019 March 2009 Conveys Draft RAI Provided by the Containment and Ventilation Branch on the Proposed Extended Power Uprate Amendment Project stage: Draft RAI ML0907809092009-03-19019 March 2009 RAI from the Containment and Ventilation Branch the Proposed Extended Power Uprate Amendment Project stage: RAI L-MT-09-017, Extended Power Uprate: Response to NRC Reactor Systems Branch & Nuclear Performance & Code Review Branch Request for Additional Information (RAI) Dated January 16, 20092009-03-19019 March 2009 Extended Power Uprate: Response to NRC Reactor Systems Branch & Nuclear Performance & Code Review Branch Request for Additional Information (RAI) Dated January 16, 2009 Project stage: Request ML0908200312009-03-20020 March 2009 Draft RAI Re. Health Physics Issues for the Proposed Extended Power Uprate Amendment Project stage: Draft RAI ML0908200992009-03-23023 March 2009 Draft RAI from the Balance of Plant Branch Re the Proposed Amendment on Extended Power Uprate Project stage: Draft RAI ML0908800022009-03-28028 March 2009 Second Portion of Draft RAI from the Mechanical and Civil Engineering Branch Regarding the Proposed Extended Power Uprate Amendment Project stage: Draft RAI ML0908800032009-03-28028 March 2009 Draft RAI from the Electrical Engineering Branch Re. the Proposed Extended Power Uprate Amendment for Monticello Project stage: Draft RAI ML0908800012009-03-29029 March 2009 Additional Draft RAI Questions from the Containment and Ventilation Branch Proposed EPU Amendment for Monticello Project stage: Draft RAI 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-23-054, Subsequent License Renewal Application Supplement 82024-01-11011 January 2024 Subsequent License Renewal Application Supplement 8 L-MT-23-047, License Amendment Request: Revision to the MNGP Pressure Temperature Limits Report to Change the Neutron Fluence Methodology and Incorporate New Surveillance Capsule Data2023-12-29029 December 2023 License Amendment Request: Revision to the MNGP Pressure Temperature Limits Report to Change the Neutron Fluence Methodology and Incorporate New Surveillance Capsule Data L-MT-23-056, Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 1 Part 22023-12-18018 December 2023 Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 1 Part 2 L-MT-23-042, 2023 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.462023-12-11011 December 2023 2023 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46 L-MT-23-052, Subsequent License Renewal Application Supplement 72023-11-30030 November 2023 Subsequent License Renewal Application Supplement 7 L-MT-23-051, Update to the Technical Specification Bases2023-11-28028 November 2023 Update to the Technical Specification Bases L-MT-23-049, Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 12023-11-21021 November 2023 Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 1 L-MT-23-043, 10 CFR 50.55a(z)(1) Request Regarding OMN-17, Revision 1. VR-092023-11-13013 November 2023 10 CFR 50.55a(z)(1) Request Regarding OMN-17, Revision 1. VR-09 L-MT-23-038, License Amendment Request to Revise Monticello Technical Specification Surveillance Requirement 3.8.6.62023-11-10010 November 2023 License Amendment Request to Revise Monticello Technical Specification Surveillance Requirement 3.8.6.6 L-MT-23-046, Subsequent License Renewal Application Response to Request for Additional Information Round 2 - Set 12023-11-0909 November 2023 Subsequent License Renewal Application Response to Request for Additional Information Round 2 - Set 1 L-MT-23-041, Subsequent License Renewal Application Response to Request for Confirmation of Information Set 22023-10-0303 October 2023 Subsequent License Renewal Application Response to Request for Confirmation of Information Set 2 L-MT-23-037, Subsequent License Renewal Application Response to Request for Additional Information Set 32023-09-22022 September 2023 Subsequent License Renewal Application Response to Request for Additional Information Set 3 L-MT-23-036, Subsequent License Renewal Application Response to Request for Additional Information Set 2 and Supplement 62023-09-0505 September 2023 Subsequent License Renewal Application Response to Request for Additional Information Set 2 and Supplement 6 L-MT-23-035, Subsequent License Renewal Application Supplement 52023-08-28028 August 2023 Subsequent License Renewal Application Supplement 5 L-MT-23-034, Subsequent License Renewal Application Response to Request for Additional Information Set 12023-08-15015 August 2023 Subsequent License Renewal Application Response to Request for Additional Information Set 1 L-MT-23-028, 2023 Refueling Outage 90-Day Inservice Inspection (ISI) Summary Report2023-07-31031 July 2023 2023 Refueling Outage 90-Day Inservice Inspection (ISI) Summary Report L-MT-23-032, 10 CFR 50.55a(z)(2) Request Regarding MO-2397, VR-112023-07-31031 July 2023 10 CFR 50.55a(z)(2) Request Regarding MO-2397, VR-11 L-MT-23-031, Subsequent License Renewal Application Supplement 4 and Responses to Request for Confirmation of Information - Set 12023-07-18018 July 2023 Subsequent License Renewal Application Supplement 4 and Responses to Request for Confirmation of Information - Set 1 L-MT-23-030, Subsequent License Renewal Application Supplement 32023-07-0404 July 2023 Subsequent License Renewal Application Supplement 3 L-MT-23-025, Subsequent License Renewal Application Supplement 22023-06-26026 June 2023 Subsequent License Renewal Application Supplement 2 L-MT-23-019, Submittal of 2022 Annual Radiological Environmental Operating Report2023-05-10010 May 2023 Submittal of 2022 Annual Radiological Environmental Operating Report L-MT-23-020, Submittal of 2022 Annual Radioactive Effluent Release Report2023-05-10010 May 2023 Submittal of 2022 Annual Radioactive Effluent Release Report L-MT-23-021, Core Operating Limits Report (COLR) for the Monticello Nuclear Generating Plant for Cycle 322023-05-0202 May 2023 Core Operating Limits Report (COLR) for the Monticello Nuclear Generating Plant for Cycle 32 L-MT-23-017, 2022 Annual Report of Individual Monitoring for the Monticello Nuclear Generating Plant (MNGP)2023-04-18018 April 2023 2022 Annual Report of Individual Monitoring for the Monticello Nuclear Generating Plant (MNGP) L-MT-23-010, Subsequent License Renewal Application Supplement 12023-04-0303 April 2023 Subsequent License Renewal Application Supplement 1 L-MT-23-013, Core Operating Limits Report (COLR) for Cycle 31, Revision 32023-03-28028 March 2023 Core Operating Limits Report (COLR) for Cycle 31, Revision 3 L-MT-23-012, Core Operating Limits Report (COLR) for Monticello Nuclear Generating Plant Cycle 31, Revision 22023-03-17017 March 2023 Core Operating Limits Report (COLR) for Monticello Nuclear Generating Plant Cycle 31, Revision 2 L-MT-23-008, 10CFR50.55a Request to Use Later Edition of ASME Section XI for ISI Code of Record (RR-003)2023-02-0707 February 2023 10CFR50.55a Request to Use Later Edition of ASME Section XI for ISI Code of Record (RR-003) L-MT-23-004, CFR 50.55a Request RR-001, Request to Use a Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI for the Monticello Third Interval Containment Inservice Inspection Program2023-01-23023 January 2023 CFR 50.55a Request RR-001, Request to Use a Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI for the Monticello Third Interval Containment Inservice Inspection Program L-MT-23-005, Response to the NRC Request for Additional Information Regarding the 50.55a Request Pr 08, HPCI Pump Quarterly Testing (EPID Number L-2022-LLR-0088)2023-01-0606 January 2023 Response to the NRC Request for Additional Information Regarding the 50.55a Request Pr 08, HPCI Pump Quarterly Testing (EPID Number L-2022-LLR-0088) L-MT-22-049, Industry Groundwater Protection Initiative Special Report2022-12-15015 December 2022 Industry Groundwater Protection Initiative Special Report L-MT-22-052, L-MT-22-052 Monticello Nuclear Generating Plant 10 CFR 50.55a Request No. Pr 08, Request for HPCI Pump Quarterly Alternative2022-12-15015 December 2022 L-MT-22-052 Monticello Nuclear Generating Plant 10 CFR 50.55a Request No. Pr 08, Request for HPCI Pump Quarterly Alternative L-MT-22-046, 2022 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.462022-12-13013 December 2022 2022 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46 L-MT-22-048, Update to the Monticello Technical Specification Bases2022-11-28028 November 2022 Update to the Monticello Technical Specification Bases L-MT-22-047, Withdrawal of Request for Relief from ASME OM Code for the Sixth Inservice Testing Interval2022-11-10010 November 2022 Withdrawal of Request for Relief from ASME OM Code for the Sixth Inservice Testing Interval L-MT-22-045, Letter Submitting Post-Exam Package2022-11-0404 November 2022 Letter Submitting Post-Exam Package L-MT-22-030, Sixth Interval Inservice Testing (1ST) Plan2022-09-0606 September 2022 Sixth Interval Inservice Testing (1ST) Plan L-MT-22-037, Supplement to 10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval, Alternative VR-10, Excess Flow Check Valve Testing Frequency2022-08-29029 August 2022 Supplement to 10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval, Alternative VR-10, Excess Flow Check Valve Testing Frequency L-MT-22-007, Response to Request for Additional Information for the Monticello Nuclear Generating Plant Alternative Request VR-08 (EPID: L-MT-22-007)2022-07-22022 July 2022 Response to Request for Additional Information for the Monticello Nuclear Generating Plant Alternative Request VR-08 (EPID: L-MT-22-007) L-MT-22-026, Changes to the Emergency Plan2022-07-19019 July 2022 Changes to the Emergency Plan L-MT-22-024, Response to a Request for Additional Information for the Monticello Nuclear Generating Plant Related to the Amendment to Adopt Advanced Framatome Methodologies2022-06-0606 June 2022 Response to a Request for Additional Information for the Monticello Nuclear Generating Plant Related to the Amendment to Adopt Advanced Framatome Methodologies L-MT-22-022, Response to a Request for Additional Information: Monticello Alternative VR-10, Excess Flow Check Valve Testing Frequency2022-05-25025 May 2022 Response to a Request for Additional Information: Monticello Alternative VR-10, Excess Flow Check Valve Testing Frequency L-MT-22-017, 2021 Annual Radiological Environmental Operating Report2022-05-11011 May 2022 2021 Annual Radiological Environmental Operating Report L-MT-22-018, 2021 Annual Radioactive Effluent Release Report2022-05-11011 May 2022 2021 Annual Radioactive Effluent Release Report L-MT-22-016, 2021 Annual Report of Individual Monitoring2022-04-28028 April 2022 2021 Annual Report of Individual Monitoring L-MT-22-019, Withdrawal of Requests for Relief from ASME OM Code for the Sixth Inservice Testing Interval2022-04-18018 April 2022 Withdrawal of Requests for Relief from ASME OM Code for the Sixth Inservice Testing Interval L-MT-22-010, License Amendment Request to Revise Technical Specification 3.6.1.8 Residual Heat Removal (RHR) Drywell Spray Header and Nozzle Surveillance Frequency2022-03-18018 March 2022 License Amendment Request to Revise Technical Specification 3.6.1.8 Residual Heat Removal (RHR) Drywell Spray Header and Nozzle Surveillance Frequency L-MT-22-012, Special Report for the Bypass of the Offgas Treatment Storage System2022-03-15015 March 2022 Special Report for the Bypass of the Offgas Treatment Storage System L-MT-22-008, 10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval Alternative Related to Excess Flow Check Valve Testing Frequency (L-MT-22-008)2022-03-0707 March 2022 10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval Alternative Related to Excess Flow Check Valve Testing Frequency (L-MT-22-008) L-MT-22-006, 10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval OMN-26 (L-MT-22-006)2022-02-18018 February 2022 10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval OMN-26 (L-MT-22-006) 2024-01-11
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August 19, 2009 L-MT-09-027 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Monticello Nuclear Generating Plant Docket 50-263 Renewed Facility Operating License No. DPR-22 Monticello Extended Power Uprate: Response to Instrumentation and Controls Branch RAI No. 3 dated April 6, 2009 (TAC No. MD9990)
Pursuant to 10 CFR 50.90, the Northern States Power Company, a Minnesota corporation (NSPM), requested in Reference 3 of Enclosure 1, an amendment to the Monticello Nuclear Generating Plant Renewed Operating License and Technical Specifications to increase the maximum authorized power level from 1775 megawatts thermal (MWt) to 2004 MWt.
The U.S. Nuclear Regulatory Commission (NRC) Instrumentation and Controls Branch (EICB) provided a Request for Additional Information (RAI), denoted as RAI No. 3, in an email dated April 6, 2009 (Reference 1 of Enclosure 1). This RAI requested the NSPM evaluate and affirm that the Technical Specification functions revised by the Extended Power Uprate license amendment request and that are within the scope of the NRC and industry agreement letter in Reference 2 of Enclosure 1, will have TSTF-493 style footnotes applied. Enclosure 1 provides the NSPM response to EICB RAI Number 3.
In accordance with 10 CFR 50.91, a copy of this letter is being provided to the designated Minnesota Official.
Summary of Commitments No new commitments or changes to any existing commitments are proposed by this letter.
2807 West County Road 75
- Monticello, Minnesota 55362-9637 Telephone: 763.295.5151
Document Control Desk
' L-MT-09-027 Page 2 of 2 I declare under penaltypf perjury that the foregoing is true and correct.
resident, Monticello Nuclear Generating Plant site Northe States Power Company - Minnesota cc: Administrator, Region Ill, USNRC Project Manager, Monticello, USNRC Resident Inspector, Monticello, USNRC Minnesota Department of Commerce
ENCLOSURE 1 MONTICELLO NUCLEAR GENERATING PLANT NSPM RESPONSE TO EICB RAI NO. 3 DATED APRIL 6, 2009
L-MT-09-027 Page 1 of 5 NRC EICB RAI No. 3:
Please affirm that all setpoints or allowable value changes in Technical Specifications, within scope of the agreement letter of February 23, 2009, will have the footnotes applied. The Background below provides the context to the request for this item.
========== Background to RAI-EICB-item 3 ==============
In the license amendment request (LAR) for extended power uprate which was submitted on November 5, 2008, Nuclear Management Company, LLC (the licensee) requested allowable value changes for various Monticello Technical Specification functions. In the LAR the licensee claimed that these functions did not meet the identified criteria for Limiting Safety System Settings (LSSS) that protect a Safety Limit that was under development by the BWR Owners Group in support of Technical Specification Task Force (TSTF)-493, Revision 3, and, therefore, did not propose to add TSTF-493 footnotes for these functions.
Since 2008, discussions between industry and the staff have resulted in agreement on the scope of TS functions which should be annotated with footnotes in TSTF-493 as well as agreement on strategies for adopting TSTF-493. These agreements for the development and adoption of TSTF-493, Revision 4, are reflected in the TSTF letter to the NRC, Industry Plan to Resolve TSTF-493, Clarify Application of Setpoint Methodology for LSSS Functions, dated February 23, 2009 (ML090540849). The TSTF agreement letter states that TSTF-493 footnotes should be added to all instrument functions in the LCOs for Reactor Trip System (also called Reactor Protection System), the Engineered Safety Feature Actuation System (also called Emergency Core Cooling System) and some instrument functions in other LCOs identified by the BWROG in TSTF-493, Revision 3.
Although the content of TSTF-493, Revision 4, LCOs was finalized by the February 23, 2009 agreement letter, the TSTF-493 Bases are still being worked on. In the interim time period, until the TSTF-493 Bases are finalized and TSTF-493 is issued, it is the NRR staffs expectation that setpoint and allowable value changes that are currently under review should follow the guidance of the TSTF agreement letter. Therefore, Monticello TS functions revised by this amendment request should be annotated with TSTF-493 footnotes.
It should be noted that the licensee has adopted TSTF-493 footnotes for other TS functions for which they agreed were LSSS that protect a Safety Limit.
L-MT-09-027 Page 2 of 5 It is recommended that the licensee submit a revision to their LAR that references the TSTF agreement letter and propose TSTF-493 footnotes for these TS functions. This will ensure that the licensee complies with the requirements of 10 CFR 50.36. The staff will accept footnotes for this function that are identical to footnotes (c) and (d) that are currently included in the Monticello TS for other TS functions.
NSPM RESPONSE:
This Instrumentation and Controls Branch (EICB) RAI (Reference 1) requested the Northern States Power Company (NSPM) to affirm that all the Technical Specification (TS) setpoints or allowable values related to Extended Power Uprate (EPU) within the scope of the February 23, 2009, NRC and industry agreement letter (Reference 2) will have Technical Specification Task Force (TSTF) - 493 style footnotes applied. 7 of the EPU license amendment request (Reference 3) discussed the methodology for the instrument setpoint calculations, determination of which functions were Limiting Safety System Settings (LSSS) that protect a Safety Limit, and provided a discussion of the measures taken to address the NRC concerns expressed within the September 7, 2005, letter from the NRC to the Nuclear Energy Institute (NEI) Setpoint Methods Task Force (Reference 4). Since the November 5, 2008, submittal of the EPU license amendment request, the NRC approval of the Power Range Neutron Monitoring System (PRNMS) license amendment (Reference 7) together with the industry NRC agreement established by the February 23, 2009, agreement letter (Reference 2) have established a clear licensing basis for TS allowable value changes associated with the Monticello Nuclear Generating Plant (MNGP) EPU, as discussed below. Two allowable value changes in the MNGP technical specifications have been identified for EPU, which required evaluation against the considerations laid out in the February 23, 2009, agreement letter.
The first allowable value changes involved the Average Power Range Monitor (APRM)
Simulated Thermal Power - High function. Enclosure 1 and 2 of the EPU license amendment request (Reference 3) identified the following function within TS Table 3.3.1.1-1, Reactor Protection System (RPS) Instrumentation, as one for which a change to the stated allowable value was required:
- Function 2.b, Average Power Range Monitor Simulated Thermal Power - High (two loop operation)
Note (b) specifies the function values for single loop operation.
At a public meeting on January 8, 2009, the industry and the NRC discussed actions to resolve TSTF-493. It was agreed the industry would develop and submit a course of action for resolution. This proposed course of action was described in a letter from the TSTF to the NRC entitled, Industry Plan to Resolve TSTF-493, Clarify Application of
L-MT-09-027 Page 3 of 5 Setpoint Methodology for LSSS Functions, dated February 23, 2009 (Reference 2). As described therein, the letter provides a mutually acceptable approach incorporating both industry and NRC concerns and preferences. The section discussing the scope of functions to be addressed states:
In order to reach resolution with the NRC on TSTF-493, the industry agrees to add the TSTF-493 footnotes to all instrument functions in the LCOs for the Reactor Trip System (also called Reactor Protection System), the Engineered Safety Feature Actuation System (also called Emergency Core Cooling System) and some instrument functions in other LCOs identified by the BWROG in TSTF-493, Revision 3.
Attachment A, "Identification of Functions to be Annotated with the TSTF-493 Footnotes," includes the disposition of Functions to be included in TSTF-493.
The indicated generic dispositions were discussed with the NRC in a teleconference held on February 11, 2009 and the NRC staff agreed that the Attachment indicates those functions applicable to all licensees for which no plant-specific analysis is required.
Licensees may choose to submit analysis to support plant-specific deviations from the list when adopting TSTF-493.
Reference 2 indicates that licensees with licensing actions in process during the development, review and approval of TSTF-493, Revision 4, are encouraged to apply approaches consistent with those proposed in Reference 2, with the exception that the TSTF-493 footnotes would be applied only to the specific setpoints being changed.
In conjunction with the licensing of the digital Power Range Neutron Monitoring System (PRNMS) (Reference 5), several of the same functions required to be revised under EPU were modified. The APRM Simulated Thermal Power - High function (Function 2.b), which is being revised to reflect the higher power level under EPU, was one of the functions included and revised as part of PRNMS license amendment request. In the response to an RAI (Reference 6) associated with the PRNMS license amendment request, the NSPM established that several functions, including this one, did not meet the criteria for Limiting Safety System Settings (LSSS) that protect a Safety Limit, and, hence did not propose to add TSTF-493 type footnotes for these functions.
The U.S. Nuclear Regulatory Commission (NRC) Staff agreed with this assessment and within the Safety Evaluation for PRNMS (Amendment 159), dated January 30, 2009 (Reference 7), indicated that the Simulated Thermal Power - High function in TS Table 3.3.1.1-1, for both single and two loop operational conditions, is not a LSSS that protects a Safety Limit.(1)
- 1. U.S. NRC Safety Evaluation Section 3.3, Setpoint Methodology, page 12, last paragraph.
L-MT-09-027 Page 4 of 5 In addressing the setpoint methodology issues, the licensee identified TS Table 3.3.1.1-1, Function 2.a, APRM Neutron Flux-High (Setdown), Function 2.b, APRM Simulated Thermal Power - High, and Function 2.f, OPRM Upscale, as functions that are not LSSS SL-related. The NRC staff agrees with the licensees determination that the above functions are not LSSS.
Therefore, in accordance with the plant-specific analysis provided by the NSPM as approved by the NRC Safety Evaluation for the PRNMS amendment, the NSPM is not proposing TSTF-493 style footnotes for the APRM Simulated Thermal Power - High function.
The second allowable value change involved a change to the Main Steam Line Flow -
High function. It was identified that Function 1.c within TS Table 3.3.6.1-1, Primary Containment Isolation Valves, which provides isolation of the Main Steam Lines on high flow, should also have been revised as part of the EPU license amendment request as a function requiring a change to the associated allowable value. The allowable value for Function 1.c within TS Table 3.3.6.1-1 will be revised as follows:
Current Proposed Allowable Value Allowable Value Function 1.c, Main Steam Line 142 percent 123.6 percent Flow - High The revision to the allowable value for Function 1.c will be provided to the NRC in a separate letter.
Attachment A to Reference 2, "Identification of Functions to be Annotated with the TSTF-493 Footnotes," provides the disposition of Functions to be included in TSTF-493.
As stated in Reference 2:
The indicated generic dispositions were discussed with the NRC in a teleconference held on February 11, 2009 and the NRC staff agreed that the Attachment indicates those functions applicable to all licensees for which no plant-specific analysis is required.
The Main Steam Line Flow - High function (Function 1.c) in TS Table 3.3.6.1-1 is not included in the list of functions contained in Attachment A (see section for NUREG-1433, Boiling Water Reactor / 4 Plants) and hence application of the interim TSTF-493 style footnotes is not required nor is proposed for this function by the NSPM.
Conclusion In accordance with the NRC Safety Evaluation for the PRNMS license amendment, the NSPM is not adopting interim TSTF-493 footnotes for the APRM Simulated Thermal
L-MT-09-027 Page 5 of 5 Power - High function. Also, in accordance with the NRC agreed upon guidance within Attachment A to the TSTF letter entitled, Industry Plan to Resolve TSTF-493, Clarify Application of Setpoint Methodology for LSSS Functions, dated February 23, 2009, the NSPM is not proposing interim TSTF-493 footnotes for the Main Steam Line Flow -
High function, because the notes are not applicable. No TS allowable values that were modified for EPU require adoption of the TSTF-493 footnotes and the NSPM is not proposing their adoption.
REFERENCES
- 1. Email K. Feintuch (NRC) to K. Pointer (NSPM), dated April 6, 2009, MD9990-Monticello EPU Additional RAI Item, (TAC No. MD999)
(Accession No. ML091030034)
- 2. Letter from the Technical Specification Task Force (TSTF) to the NRC, TSTF-09-07, Industry Plan to Resolve TSTF-493, "Clarify Application of Setpoint Methodology for LSSS Functions", dated February 23, 2009. (ADAMS Ascension No. ML090540849)
- 3. NSPM letter to NRC, License Amendment Request: Extended Power Uprate, (L-MT-08-052), dated November 5, 2008. (ADAMS Accession No. ML083230111)
- 4. NRC to NEI (NEI Setpoint Methods Task Force), Technical Specification for Addressing Issues Related to Setpoint Allowable Values, dated September 7, 2005. (ADAMS Accession No. ML0525000004)
- 5. NSPM letter to NRC, License Amendment Request: Power Range Neutron Monitoring System Upgrade, (L-MT-08-004), dated February 6, 2008. (ADAMS Accession No. ML08344081)
- 6. NSPM letter to NRC, Response to Requests for Additional Information for License Amendment Request for Power Range Neutron Monitoring Svstem Upgrade (TAC No. MD8064), (L-MT-08-049), dated September 16, 2008.
(ADAMS Accession No. ML082620582)
- 7. NRC letter to NSPM, Monticello Nuclear Generating Plant (MNGP) -Issuance of Amendment Regarding the Power Range Neutron Monitoring System (TAC No. MD8064), dated January 30, 2009. (ADAMS Accession No. ML083440681)