Letter Sequence Supplement |
---|
TAC:MD9990, Clarify Application of Setpoint Methodology for LSSS Functions (Approved, Closed) 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
|
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
[Table View] |
|
---|
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] |
Text
ENCLOSURE 4 CONTAINS PROPRIETARY INFORMATION WITHHOLD FROM PUBLIC DISCLOSURE IN ACCORDANCE WITH 10 CFR 2.390 Xcel Energy Monticello Nuclear Generating Plant 2807 W County Rd 75 Monticello, MN 55362 June 27, 2012 L-MT-12-054 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Monticello Nuclear Generating Plant Docket 50-263 Renewed License No. DPR-22
Subject:
Supplement to Maximum Extended Load Line Limit Analysis Plus License Amendment Request (TAC ME3145)
References:
- 1) Letter from T J O'Connor (NSPM), to Document Control Desk (NRC),"License Amendment Request: Maximum Extended Load Line Limit Analysis Plus," L-MT-10-003, dated January 21, 2010. (ADAMS Accession No. ML100280558)
- 2) Letter from T J O'Connor (NSPM) to Document Control Desk (NRC),"
Subject:
Monticello Extended Power Uprate: Replacement Steam Dryer Supplement (TAC MD9990)," L-MT-10-046, dated June 30, 2010. (ADAMS Accession No. ML1 02010462)3) NEDC-33006P-A, Revision 3, "Licensing Topical Report, General Electric Boiling Water Reactor, Maximum Extended Load Line Limit Analysis Plus," dated June 2009. (ADAMS Accession No.ML091800512)
- 4) Letter from P S Tam (NRC) to T J O'Connor (NSPM), "
Subject:
Monticello Nuclear Generating Plant -Determination that Submitted Information is Proprietary and Will Be Withheld from Public Disclosure (TAC No. ME3145)," dated February 16, 2010. (ADAMS Accession No. ML100320229)
In Reference 1, Northern States Power Company, a Minnesota corporation (NSPM), doing business as Xcel Energy, requested approval of an amendment to the Monticello Nuclear Generating Plant (MNGP) Renewed Operating License (OL) and Technical Document Control Desk Page 2 Specifications (TS). The proposed change would allow operation in the expanded Maximum Extended Load Line Limit Analysis Plus (MELLLA+)
domain.In Reference 2, NSPM provided analyses for a Replacement Steam Dryer (RSD) for MNGP. A portion of these analyses concern the potential effect of moisture carryover (MCO) on plant operation in conjunction with the MNGP Extended Power Uprate (EPU)license amendment request (LAR). Enclosure 1 to this letter contains an evaluation of the effects of the installation of a RSD on the MELLLA+ LAR. The RSD supplement was provided to the NRC in Reference
- 2. The evaluation concludes that there are no effects on the MELLLA+ LAR.Enclosure 2 to this letter contains corrected pages for NEDC-33435P, Revision 1 and NEDO-33435, Revision 1, based on an error discovered on Table 1-1 of these documents.
NEDC-33435P, Revision 1 and NEDO-33435, Revision 1 were originally provided to the NRC in Reference 1.Enclosure 3 to this letter contains a MNGP cycle 26 supplemental reload licensing report (SRLR) that includes MELLLA+ conditions and evaluations.
The cycle 26 SRLR is being submitted to the NRC to fulfill the requirements of the MELLLA+ topical report (Reference 3), Limitation and Condition 12.4, which specifies that the SRLR for the initial MELLLA+ implementation cycle shall be submitted for NRC staff confirmation.
Enclosure 4 to this letter contains a clarification regarding application of administrative controls described in the original MELLLA+ LAR (Reference 1). This clarification forms the basis for a correction to NEDC-33435P, Revision 1.Information in Enclosure 4 is considered proprietary to General Electric -Hitachi. No new information is being provided; however, to fully describe the clarification required, it was necessary to include excerpts of proprietary information from NEDC-33435P, Revision 1, which was included in Reference 1, Attachment
- 3. Since this information has been previously accepted by the NRC as proprietary information withheld from public disclosure (Reference 4), no new request for withholding or affidavit has been provided as the original request for withholding and affidavit (provided in Reference 1, Attachment
- 4) is applicable to this information.
This letter makes no new commitments and no revisions to existing commitments.
Document Control Desk Page 3 I declare under penalty of perjury that the foregoing is true and correct.Executed on: June Z7, 2012 Mark A. Schimmel Site Vice-President Monticello Nuclear Generating Plant Northern States Power Company-Minnesota Enclosures (4)cc: Regional Administrator, Region Ill, USNRC (w/o enclosures)
Project Manager, Monticello Nuclear Generating Plant, USNRC Resident Inspector, Monticello Nuclear Generating Plant, USNRC (w/o enclosures)
Minnesota Department of Commerce (w/o enclosures)
L-MT-12-054 ENCLOSURE I EVALUATION OF REPLACEMENT STEAM DRYER ON MELLLA+ LICENSE AMENDMENT REQUEST 6 pages follow L-MT-12-054 Enclosure 1 Page 1 of 6 The purpose of this table is to demonstrate that installation of the replacement steam dryer (RSD) does not impact the analyses provided in the Maximum Extended Load Line Limit Analysis Plus (MELLLA+)
application for Monticello Nuclear Generating Plant (MNGP). Reference E1-1, Attachment 3 indicated that the MELLLA+ analysis determined that the moisture content of the steam leaving the vessel may increase up to 0.5 wt% at times while operating near the minimum core flow in the MELLLA+ operating domain. Operation at this point in the MELLLA+ domain would be experienced infrequently.
As the table below indicates, 0.5 wt% is the level of moisture carryover (MCO) that has been evaluated for MELLLA+.The first two columns in the table below list the MELLLA+ submittal and text location that describes the previously installed steam dryer (PISD) or analyses that used PISD parameters.
The third column describes the contents (text) that are under review. The final column dispositions the text under review and determines that no actions or resolutions are required.Letter No. Locations Applicable Contents/issues Required Actions or Resolution ADAMS No. Evaluated L-MT-10-003, M+ Attachment 3, The 4 th paragraph has the statement: "There is a The MOO assumed for Extended Power LAR NEDC-33435P, potential increase in the steam moisture content Uprate (EPU) and MELLLA+ is 0.5% by ML100280558 Executive.
at certain times while operating in the MELLLA+ weight, while the estimated MCO for the Summary pg xii operating domain. The effects of the potential RSD is < 0.14% by weight. Thus, the increase in moisture content on plant hardware MELLLA+ SAR basis and evaluation have been evaluated and determined to be results bound MELLLA+ operation with acceptable." the RSD. Therefore, no change is required.L-MT-10-003, M+ Attachment 3, The 3 rd paragraph has the statement: "There is a The MCO assumed for EPU and LAR NEDC-33435P, potential increase in the steam moisture content MELLLA+ is 0.5% by weight, while the ML100280558 S1.0 pg 1-1 at certain times while operating in the MELLLA+ estimated MCO for the RSD is <0.14%operating domain. The effects of the potential by weight. Thus, the MELLLA+ SAR increase in moisture content on plant hardware basis and evaluation results bound have been evaluated and determined to be MELLLA+ operation with the RSD.acceptable." Therefore, no change is required.
L-MT-12-054 Enclosure 1 Page 2 of 6 Letter No. Locations Applicable Contents/Issues Required Actions or Resolution ADAMS No. Evaluated L-MT-10-003, M+ Attachment 3, Section 1.1.4, when referring to Section 8.0 The MCO assumed for EPU and LAR NEDC-33435P, states: "However, slightly higher loading of the MELLLA+ is 0.5% by weight, while the ML100280558 S1.1.4 pg 1-4 condensate demineralizers is possible if the estimated MCO for the RSD is <0.14%moisture carryover (MCO) in the reactor steam by weight. Thus, the MELLLA+ SAR increases.
The radiological consequences are basis and evaluation results bound evaluated to show that applicable regulations are MELLLA+ operation with the RSD.met." Therefore, no change is required.L-MT-10-003, M+ Attachment 3, Section 3.3.6 addresses "Steam Separator and The MCO assumed for EPU and LAR NEDC-33435P, Dryer Performance" and states: MELLLA+ is 0.5% by weight, while the ML100280558 S3.3.6 pg 3-8 "The evaluation of steam separator and dryer estimated MCO for the RSD is < 0.14%performance at MELLLA+ conditions indicates an by weight. Thus, the MELLLA+ SAR increase in MCO will occur. The effect of basis and evaluation results bound increasing steam moisture content has been MELLLA+ operation with the RSD.analyzed and is discussed in the following Therefore, no change is required.sections of this report: a. 3.5.1 Reactor Coolant Pressure Boundary Piping b. 8. 1 Liquid and Solid Waste Management
- c. 8.4.2 Fission and Activation Corrosion Products d. 8.5 Radiation Levels e. 10.4 Testing f 10. 7.2 Flow Accelerated Corrosion The effect of increased MCO on plant operation has been analyzed to verify acceptable steam separator-dryer performance under MELLLA +operating conditions.
MCO is monitored during operation to ensure adequate operating limitations are implemented as required to maintain MCO within analyzed conditions."
L-MT-12-054 Enclosure 1 Page 3 of 6 Letter No. Locations Applicable Contents/issues Required Actions or Resolution ADAMS No. Evaluated L-MT-10-003, M+ Attachment 3, Section 3.4.2 addresses "FIV Influence on The conclusion that MELLLA+ does not LAR NEDC-33435P, Reactor Internals," and lists the steam dryer as increase the steam flow is not changed ML100280558 S3.4.2 pg 3-10 one of the reviewed components.
by the introduction of the RSD. Thus, the RSD does not affect the Flow Induced Vibration (FIV) evaluation for MELLLA+.L-MT-10-003, M+ Attachment 3, Section 3.5.1.1 addresses "Main Steam and The MCO assumed for EPU and LAR NEDC-33435P, Feedwater Piping Inside Containment." MELLLA+ is 0.5% by weight, while the ML100280558 S3.5.1.1 pgs 3- The 3 rd paragraph has the statement:
estimated MCO for the RSD is < 0.14%12, 3-13 "...as discussed in Section 3.3.6, the MCO may by weight. Thus, the MELLLA+ SAR basis and evaluation results bound increase for a period of time during the cycle Mas operation with thuRd when a plant is operating at or near the MELLLA+ operation with the RSD.MELLLA+ minimum core flow rate. The time that Therefore, no change is required.a plant spends in this flow condition is not excessive.
The generic disposition concludes that the change in erosion/corrosion rates as a result of increased carryover is adequately managed by the existing programs discussed in Section 10. 7." The 4 th paragraph has the statement:
"...the MCO for Monticello may increase to a maximum of 0. 5 wt% for a period of time during the cycle when Monticello is operating at or near the MELLLA+ minimum core flow rate.Monticello implements programs adequate to manage this change in the erosion/corrosion rate as described in Section 10. 7."
L-MT-12-054 Enclosure 1 Page 4 of 6 Letter No. Locations Applicable Contents/issues Required Actions or Resolution ADAMS No. Evaluated L-MT-10-003, M+ Attachment 3, Section 8.1.2 addresses "Waste Volumes," and The MCO assumed for EPU and LAR NEDC-33435P, the effects of potentially higher MCO. The MELLLA+ is 0.5% by weight, while the ML100280558 S8.1.2 pg 8-1 MELLLA+ SAR's MCO related evaluations and estimated MCO for the RSD is 0.14%conclusions are based on a MCO of 0.5%. by weight. Thus, the MELLLA+ SAR basis and evaluation results bound MELLLA+ operation with the RSD.Therefore, no change is required.L-MT-10-003, M+ Attachment 3, Section 8.4.2 addresses "Fission and Activation The MCO assumed for EPU and LAR NEDC-33435P, Corrosion Products," which could increase with MELLLA+ is 0.5% by weight, while the ML100280558 S8.4.2 pg 8-4 increased MCO. The Section's evaluation and estimated MCO for the RSD is 0.14%conclusion are based on a MCO of 0.5%. by weight. Thus, the MELLLA+ SAR basis and evaluation results bound MELLLA+ operation with the RSD.Therefore, no change is required.L-MT-10-003, M+ Attachment 3, Section 8.5.1 addresses "Normal Operational The MCO assumed for EPU and LAR NEDC-33435P, Radiation Levels," and Section 8.5.2 addresses MELLLA+ is 0.5% by weight, while the ML100280558 S8.5.1, S8.5.2 "Post-Shutdown Radiation Levels" both of which estimated MCO for the RSD is 0.14%pgs 8-5, 8-6 could increase with increased MCO. These by weight. Thus, the MELLLA+ SAR evaluations and conclusions in these sections basis and evaluation results bound are based on a MCO of 0.5%. MELLLA+ operation with the RSD.Therefore, no change is required.L-MT-10-003, M+ Attachment 3, Section 10.4.1 addresses "Steam Separator-The information in Section 10.4.1 is LAR NEDC-33435P, Dryer Performance" testing. applicable to any steam dryer, and does ML100280558 S10.4.1 pg 10-4 not conflict with any information regarding the RSD. Therefore, this section does not require change.
L-MT-12-054 Enclosure 1 Page 5 of 6 Letter No. Locations Applicable Contents/issues Required Actions or Resolution ADAMS No. Evaluated L-MT-10-003, M+ Attachment 3, Section 10.7.2 includes addressing the MCO The MCO assumed for EPU and LAR NEDC-33435P, effects on "Flow Accelerated Corrosion." MELLLA+ is 0.5% by weight, while the ML100280558 S10.7.2 pgs 10- estimated MCO for the RSD is < 0.14%8, 10-9 by weight. Thus, the MELLLA+ SAR basis and evaluation results bound MELLLA+ operation with the RSD.Therefore, no change is required.L-MT-10-003, M+ Attachment 5, Attachment 5 is a nonproprietary version of This document does not require reissue LAR NEDO-33435 Attachment
- 3. as no proprietary changes have been ML100280558 made. No changes are proposed for Attachment 3, therefore, no changes to Attachment 5 are required.L-MT-10-003, M+ Attachment 6, Item T0304 addresses "Reactor Internal MELLLA+ does not involve increased LAR Risk Pressure Differences
& Fuel Lift Evaluation." flows, and thus, the T0304 is not ML100280558 Assessment, affected.
The Reactor Internal Pressure Table 3-1, Differential (RIPD) methodology was T0304, pg 3-10 discussed in enclosure 8 of L-MT-10-046 and no change to the MELLLA+evaluation is required.L-MT-10-003, M+ Attachment 6, Item T0306 addresses "Steam Dryer/Separator The MCO assumed for EPU and LAR Risk Performance," and discusses the effects of MELLLA+ is 0.5% by weight, while the ML100280558 Assessment, MCO. estimated MCO for the RSD is < 0.14%Tab. 3-1, T0306, by weight. Thus, the MELLLA+ SAR pg 3-10 basis and evaluation results bound MELLLA+ operation with the RSD.Therefore, no change is required.
L-MT-12-054 Enclosure 1 Page 6 of 6 Letter No. Locations Applicable Contents/issues Required Actions or Resolution ADAMS No. Evaluated L-MT-10-017, M+ Attachment 1, RAI 2 requests MCO information, which is based The MCO assumed for EPU and Supplement for NRC Acceptance on the PISD. MELLLA+ is 0.5% by weight, while the Acceptance Review RAI 2, estimated MCO for the RSD is < 0.14%Review pgs 2, 3 by weight. Thus, the MELLLA+ SAR ML100710445 basis and evaluation results bound MELLLA+ operation with the RSD.Therefore, no change is required.Conclusion Based on the reviews provided above, no changes to any MELLLA+ documentation are required based on the installation of a replacement steam dryer.References El-1 Letter from T J O'Connor (NSPM), to Document Control Desk (NRC), "License Amendment Request: Maximum Extended Load Line Limit Analysis Plus," L-MT-1 0-003, dated January 21, 2010. (ADAMS Accession No.ML100280558)
L-MT-12-054 ENCLOSURE 2 Corrected Pages for NEDC-33435P, Revision I and NEDO-33435, Revision 1 In a letter from General Electric-Hitachi (GEH) dated March 24, 2010, GEH described a typographical error discovered in Table 1-1 of NEDC-33435P, Revision 1 and its companion document NEDO-33435, Revision 1 (non-proprietary version of NEDC-33435P). NEDC-33435P, Revision 1 was provided to the NRC as attachment 3 of enclosure 1 of reference E2-1 and NEDO-33435, Revision 1 was provided to the NRC as attachment 5 of enclosure 1 of reference E2-1.Table 1-1 of NEDC-33435P, Revision 1 identifies computer codes that were used in the production of the Maximum Extended Load Line Limit Analysis Plus (MELLLA+)
Safety Analysis Report (SAR). The table incorrectly identified that the computer code ODYN version 09 was used in the production of the MELLLA+ SAR. Rather Table 1-1 should have identified that ODYN version 10 was used in the production of the MELLLA+ SAR.The corrected pages are attached.
The attached corrected pages do not contain GEH proprietary information.
References:
E2-1 Letter from T J O'Connor (NSPM), to Document Control Desk (NRC), "License Amendment Request: Maximum Extended Load Line Limit Analysis Plus," L-MT-10-003, dated January 21, 2010. (ADAMS Accession No. ML100280558) 2 pages follow NEDC-33435P REVISION 1- CORRECTED PAGE GEH PROPRIETARY INFORMATION Table 1-1 Computer Codes Used in the M+SAR Evaluations Task Computer Version or NRC Comments Code Revision Approved Reactor Heat Balance ISCOR 09 Y(1) NEDE-2401 1 P Rev. 0 SER Reactor Core and Fuel TGBLA 06 Y(2) NEDE-30130P-A Performance PANAC 11 Y(2) NEDE-30130P-A ISCOR 09 Y(1) NEDE-24011P Rev. 0 SER Thermal Hydraulic Stability ODYSY 05 Y NEDC-33213P-A TRACG 02 Y(15) NEDC-33147P-A Rev. 2 TRACG 04 N(15)ISCOR 09 Y(1) NEDE-24011P Rev. 0 SER PANACEA 11 Y(3) NEDE-30130P-A Reactor Internal Pressure LAMB 07 (4) NEDE-20566P-A Differences TRACG 02 Y(5) NEDE-32176P, Rev. 2, Dec. 1999 NEDC-32177P, Rev. 2, Jan. 2000 NRC TAC No. M90270, Sept. 1994 ISCOR 09 Y(1) NEDE-24011P Rev. 0 SER Reactor Pressure Vessel TGBLA 06 Y(2) NEDE-30130P-A (RPV) Fluence DORTG 01 Y (12, 13) CCC-543 Annulus Pressurization ISCOR 09 Y(1) NEDE-24011P Rev. 0 SER Loads Transient Analysis PANAC 11 Y NEDE-30130P-A (6)ODYN 10 Y NEDE-24154P-A NEDC-24154P-A, Vol 4, Sup 1 ISCOR 09 Y (1) NEDE-24011P Rev. 0 SER TASC 03 Y NEDC-32084P-A Rev. 2 Anticipated Transient ODYN 10 Y NEDC-24154P-A, Vol 4, Sup 1 Without Scram (ATWS) STEMP 04 (7)PANACEA 11 Y(6)TASC 03A Y NEDC-32084P-A Rev. 2 ISCOR 09 Y(1) NEDE-24011P Rev. 0 SER TRACG 04 N(14)Containment System M3CPT 05 Y NEDO-10320, April 1971 Response LAMB 08 (4) NEDE-20566P-A, September 1986 Reactor Recirculation BILBO 04V (8) NEDE-23504, Feb. 1977 System ECCS-Loss of Coolant LAMB 08 Y NEDE-20566P-A Accident (LOCA) GESTR 08 Y NEDE-23785-1P-A, Rev. 1 SAFER 04 Y (9)(10) (11)ISCOR 09 Y(1) NEDE-24011P Rev. 0 SER TASC 03 Y NEDC-32084P-A
- The application of these codes to the MELLLA+ analyses complies with the limitations, restrictions, and conditions specified in the approving NRC SER where applicable for each code. The application of the codes also complies with the SERs for the extended power uprate programs.1-10 NEDO-33435 REVISION 1 -CORRECTED PAGE NON-PROPRIETARY INFORMATION Table 1-1 Computer Codes Used in the M+SAR Evaluations Task Computer Version or NRC Comments Code Revision Approved Reactor Heat Balance ISCOR 09 Y(1) NEDE-2401 IP Rev. 0 SER Reactor Core and Fuel TGBLA 06 Y(2) NEDE-30130P-A Performance PANAC 11 Y(2) NEDE-30130P-A ISCOR 09 Y(1) NEDE-24011P Rev. 0 SER Thermal Hydraulic Stability ODYSY 05 Y NEDC-33213P-A TRACG 02 Y(15) NEDC-33147P-A Rev. 2 TRACG 04 N(15)ISCOR 09 Y(1) NEDE-24011P Rev. 0 SER PANACEA 11 Y(3) NEDE-30130P-A Reactor Internal Pressure LAMB 07 (4) NEDE-20566P-A Differences TRACG 02 Y(5) NEDE-32176P, Rev. 2, Dec. 1999 NEDC-32177P, Rev. 2, Jan. 2000 NRC TAC No. M90270, Sept. 1994 ISCOR 09 Y(1) NEDE-24011P Rev. 0 SER Reactor Pressure Vessel TGBLA 06 Y(2) NEDE-30130P-A (RPV) Fluence DORTG 01 Y (12, 13) CCC-543 Annulus Pressurization ISCOR 09 Y(1) NEDE-2401 1 P Rev. 0 SER Loads Transient Analysis PANAC 11 Y NEDE-30130P-A (6)ODYN 10 Y NEDE-24154P-A NEDC-24154P-A, Vol 4, Sup 1 ISCOR 09 Y (1) NEDE-2401 1 P Rev. 0 SER TASC 03 Y NEDC-32084P-A Rev. 2 Anticipated Transient ODYN 10 Y NEDC-24154P-A, Vol 4, Sup 1 Without Scram (ATWS) STEMP 04 (7)PANACEA 11 Y(6)TASC 03A Y NEDC-32084P-A Rev. 2 ISCOR 09 Y(1) NEDE-24011P Rev. 0 SER TRACG 04 N(14)Containment System M3CPT 05 Y NEDO-10320, April 1971 Response LAMB 08 (4) NEDE-20566P-A, September 1986 Reactor Recirculation BILBO 04V (8) NEDE-23504, Feb. 1977 System ECCS-Loss of Coolant LAMB 08 Y NEDE-20566P-A Accident (LOCA) GESTR 08 Y NEDE-23785-1P-A, Rev. 1 SAFER 04 Y (9)(10) (11)ISCOR 09 Y(1) NEDE-24011P Rev. 0 SER TASC 03 Y NEDC-32084P-A
- The application of these codes to the MELLLA+ analyses complies with the limitations, restrictions, and conditions specified in the approving NRC SER where applicable for each code. The application of the codes also complies with the SERs for the extended power uprate programs.1-10