Letter Sequence Other |
|---|
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:Graphics incl Charts and Tables
MONTHYEARML24109A1102024-04-17017 April 2024
1 to the Updated Safety Analysis Report, List of Effective Pages
ML24092A2152024-03-27027 March 2024
Email: Requests for Information to Support Deis
L-MT-21-068, 2021 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.462021-12-15015 December 2021
2021 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46
L-MT-18-071, Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.462018-12-12012 December 2018
Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46
ML16245A7202016-09-16016 September 2016
MSFHI Tables Final 8-31-2016
ML16056A1392016-03-11011 March 2016
Correction to the U.S. Nuclear Regulatory Commission Analysis of Licensees' Decommissioning Funding Status Reports
ML14307B7072014-12-10010 December 2014
Supplemental Information Related to Development of Seismic Risk Evaluations for Information Request Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-T
L-MT-14-054, Thirty-Day Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.462014-06-17017 June 2014
Thirty-Day Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46
ML14141A3992014-05-27027 May 2014
Correction Letter for License Amendment No. 180 Maximum Extended Load Line Limit Plus (Mellla+)
ML13105A1882013-04-10010 April 2013
Monticello Extended Power Uprate (Epu): Response to Request for Additional Information - Electrical Engineering Branch (TAC MD9990), Page 1 of 96 Through Page 57 of 96
L-MT-13-034, Extended Power Uprate (Epu): Response to Request for Additional Information - Electrical Engineering Branch (TAC MD9990), Page 58 of 96 Through End2013-04-10010 April 2013
Extended Power Uprate (Epu): Response to Request for Additional Information - Electrical Engineering Branch (TAC MD9990), Page 58 of 96 Through End
L-MT-08-058, Thirty (30) Day Notification Pursuant to 10CFR72.212, Conditions of General License Issued Under 6 72.210, for Storage of Spent Fuel2008-10-16016 October 2008
Thirty (30) Day Notification Pursuant to 10CFR72.212, Conditions of General License Issued Under 6 72.210, for Storage of Spent Fuel
ML0728203072007-10-11011 October 2007
Electronic Distribtion Initiative Letter, Licensee List, Electronic Distribution Input Information, Division Plant Mailing Lists
ML0612402692006-06-0505 June 2006
Attachment 6 - Table R - Relocated Specifications for Monticello, Amendment 146 for the Conversion to the Improved Technical Specifications with Beyond-Scope Issues
ML0612402662006-06-0505 June 2006
Attachment 5 - Table La - Removed Details for Monticello, Amendment 146 for the Conversion to the Improved Technical Specifications with Beyond-Scope Issues
ML0612402642006-06-0505 June 2006
Attachment 4 - Table L - Less Restrictive Changes for Monticello, Amendment 146 for the Conversion to the Improved Technical Specifications with Beyond-Scope Issues
ML0612402592006-06-0505 June 2006
Attachment 3 - Table M - More Restrictive Changes for Monticello, Amendment 146 for the Conversion to the Improved Technical Specifications with Beyond-Scope Issues
ML0612402552006-06-0505 June 2006
Attachment 2 - Table a - Administrative Changes for Monticello, Amendment 146 for the Conversion to the Improved Technical Specifications with Beyond-Scope Issues
ML0613901442005-08-0404 August 2005
Web References for Monticello Dseis: Socioeconomics
ML0520105032005-08-0101 August 2005
Xcel Energy - Migratory Bird Reporting Form and Flow Chart, Revised 2003
ML0520104582005-04-11011 April 2005
NCDC Listing of Nonattainment Status for Each County by Year, as of April 11, 2005
ML0434501802003-12-11011 December 2003
NMC Program Health Status Fleet Program at a Glance
2024-04-17
[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
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 May 27, 2014 Karen D. Fili Site Vice President Monticello Nuclear Generating Plant Northern States Power Company - Minnesota 2807 West County Road 75 Monticello, MN 55362-9637
SUBJECT:
MONTICELLO NUCLEAR GENERATING PLANT- CORRECTION LETTER FOR AMENDMENT NO. 180 TO RENEWED FACILITY OPERATING LICENSE RE:
MAXIMUM EXTENDED LOAD LINE LIMIT PLUS (MELLLA+) (TAC NO. ME3145)
Dear Mrs. Fili:
On March 28, 2014, the U.S. Nuclear Regulatory Commission (NRC) issued Amendment No. 180 to Renewed Facility Operating License No. DPR-22 for the Monticello Nuclear Generating Plant (Agencywide Documents Access and Management System (ADAMS)
Package Accession No. ML14070A042).
On May 19, 2014, the NRC staff was informed by a member of your staff that an error had been identified on Technical Specification (TS) Table 3.3.1.1-1, "Reactor Protection System Instrumentation," Function 2.f., "OPRM Upscale," of the issued amendment. Specifically, in its MELLLA+ application dated January 21, 2012 (ADAMS Accession No. ML100280558),
Northern States Power Company requested that the Allowable Value be changed from "As specified in COLR" to "NA", consistent with Section 8 of approved topical report General Electric Nuclear Energy NEDC-33075P-A, Revision 6, "Detect and Suppress Solution -Confirmation Density Licensing Topical Report," dated January 2008 (ADAMS Accession Package No.
ML080310384). In the approved License Amendment No. 180, the Allowable Value of "NA" was inadvertently omitted from Function 2.f of Table 3.3.1.1-1 on TS page 3.3.1.1-8.
The NRC staff concludes that the error was introduced during preparation of the license amendment and is entirely editorial in nature. The proposed correction does not change any of the conclusions in the safety evaluation associated with the amendment and does not affect the associated notice to the public. Please find enclosed the replacement page.
K. Fili If you have any questions regarding this matter, please call me at (301) 415-3049.
Sincerely,
~ Terry A. Beltz, Senior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-263
Enclosure:
Corrected Page to License Amendment No. 180 cc w/encl: Distribution via ListServ
ENCLOSURE MONTICELLO NUCLEAR GENERATING PLANT DOCKET NO. 50-263 CORRECTED PAGE TO LICENSE AMENDMENT NO. 180 TECHNICAL SPECIFICATIONS PAGE 3.3.1.1-8
RPS Instrumentation 3.3.1.1 Table 3.3.1.1-1 (page 2 of 4)
Reactor Protection System Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION D:1 REQUIREMENTS VALUE
- c. Neutron Flux- High 3(C) F SR 3.3.1.1.1 ~ 122% RTP SR 3.3.1.1.2 SR 3.3.1.1.4 SR 3.3.1.1.6 SR 3.3.1.1.11(t)(g)
SR 3.3.1.1.15
- d. lnop. 3(C) G SR 3.3.1.1.4 NA 1' 2 SR 3.3.1.1.15
- e. 2-0ut-Of-4 Voter 1' 2 2 G SR 3.3.1.1.1 NA SR 3.3.1.1.4 SR 3.3.1.1.12 SR 3.3.1.1.14 SR 3.3.1.1.15
- f. OPRM UpscaleleJ ~ 20% RTP 3(c) SR 3.3.1.1.1 NA SR 3.3.1.1.4 SR 3.3.1.1.6 SR 3.3.1.1.11 SR 3.3.1.1.15
- 3. Reactor Vessel Steam 1' 2 2 G SR 3.3.1.1.4 ~ 1075 psig Dome Pressure- High SR 3.3.1.1.7 SR 3.3.1.1.9 SR 3.3.1.1.12 SR 3.3.1.1.14
- 4. Reactor Vessel Water 1' 2 2 G SR 3.3.1.1.1 ~ 7 inches Level- Low SR 3.3.1.1.4 SR 3.3.1.1.7 SR 3.3.1.1.8 SR 3.3.1.1.11 SR 3.3.1.1.12 SR 3.3.1.1.14 (c) Each APRM I OPRM channel provides inputs to both trip systems.
(e) Following DSS-CD implementation, DSS-CD is not required to be armed while in the DSS-CD Armed Region during the first reactor startup and during the first controlled shutdown that passes completely through the DSS-CD Armed Region. However, DSS-CD is considered OPERABLE and shall be maintained OPERABLE and capable of automatically arming for operation at recirculation drive flow rates above the DSS-CD Armed Region.
(f) If the as-found channel setpoint is not the Nominal Trip Setpoint but is conservative with respect to the Allowable Value, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.
(g) The instrument channel setpoint shall be reset to the Nominal Trip Setpoint (NTSP) at the completion of the surveillance; otherwise, the channel shall be declared inoperable. The NTSP and the methodology used to determine the NTSP are specified in the Technical Requirements Manual.
Monticello 3.3.1.1-8 Amendment No. 146, 159, 175, 180 Revised by correction letter dated May 27, 2014
ML14141A399 OFFICE LPL3-1/PM LPL3-1/LA LPL3-1/BC LPL3-1/PM NAME TBeltz MHenderson RCarlson TBeltz DATE 05/21/14 05/22/14 05/22/14 05/27/14
