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| | number = ML13358A372 | | | number = ML13358A372 |
| | issue date = 12/20/2013 | | | issue date = 12/20/2013 |
| | title = Monticello - Maximum Extended Load Line Limit Analysis Plus: Cycle 27 Safety Reload Licensing Report and Request for Additional Information Response | | | title = Maximum Extended Load Line Limit Analysis Plus: Cycle 27 Safety Reload Licensing Report and Request for Additional Information Response |
| | author name = Fili K D | | | author name = Fili K D |
| | author affiliation = Northern States Power Co, Xcel Energy | | | author affiliation = Northern States Power Co, Xcel Energy |
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| | page count = 3 | | | page count = 3 |
| | project = TAC:ME3145 | | | project = TAC:ME3145 |
| | stage = Other | | | stage = Request |
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| {{#Wiki_filter:@XcelEnergyMonticello Nuclear Generating Plant2807 W County Rd 75Monticello, MN 55362December 20, 2013L-MT-1 3-12610 CFR 50.90U.S. Nuclear Regulatory CommissionATTN: Document Control DeskWashington, DC 20555-0001Monticello Nuclear Generating PlantDocket 50-263Renewed License No. DPR-22Subject: Maximum Extended Load Line Limit Analysis Plus: Cycle 27 SafetyReload Licensing Report and Request for Additional InformationResponse (TAC ME3145)References: 1)Letter from T J O'Connor (NSPM), to Document Control Desk (NRC),"License Amendment Request: Maximum Extended Load Line LimitAnalysis Plus," L-MT-10-003, dated January 21, 2010. (ADAMSAccession No. ML1100280558)2) NEDC-33006P-A, Revision 3, "Licensing Topical Report, GeneralElectric Boiling Water Reactor, Maximum Extended Load Line LimitAnalysis Plus," dated June 2009. (ADAMS Accession No.ML091800512)3) Email from T. Beltz (NRC) to J. Fields (NSPM), "Monticello NuclearGenerating Plant -Draft Request for Additional Information re:Maximum Extended Load Line Limit Analysis Plus LAR Review (TACNo. ME3145)," dated November 26, 2013.In Reference 1, Northern States Power Company, a Minnesota corporation (NSPM),doing business as Xcel Energy, requested approval of an amendment to the MonticelloNuclear Generating Plant (MNGP) Renewed Operating License (OL) and TechnicalSpecifications (TS). The proposed change would allow operation in the expandedMaximum Extended Load Line Limit Analysis Plus (MELLLA+) domain. | | {{#Wiki_filter:@XcelEnergy Monticello Nuclear Generating Plant 2807 W County Rd 75 Monticello, MN 55362 December 20, 2013 L-MT-1 3-126 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 |
| Document Control DeskPage 2The purpose of this letter is to provide the NRC with the MNGP cycle 27 SupplementalReload Licensing Report (SRLR) applicable to MELLLA+ conditions and evaluationsand to provide a response to an NRC Request for Additional Information (RAI).Enclosure 1 to this letter provides the MNGP cycle 27 SRLR applicable to MELLLA+conditions and evaluations. The cycle 27 SRLR is being submitted to the NRC to fulfillthe requirements of the MELLLA+ topical report (Reference 2), Limitation and Condition12.4, which specifies that the SRLR for the initial MELLLA+ implementation cycle shallbe submitted for NRC staff confirmation.The SRLR supports the licensing work performed for the MNGP MELLLA+ license.This reload design was initiated prior to the PRIME transition commitment to utilizePRIME for reload analyses. The cycle-specific reload analyses are based on GESTR-M,with one exception, and the peak clad temperature (PCT) impact of PRIME wasevaluated as part of 10 CFR 50.46 Error Notification 2012-01. The one exception is theDetect and Suppress Solution -Confirmation Density (DSS-CD) Backup StabilityProtection (BSP) analysis, which was performed using PRIME. The use of PRIME forthe DSS-CD BSP analysis is consistent with NEDO-33173 Supplement 4-A, Rev. 1,"Implementation of PRIME Models and Data in Downstream Methods," November 2012.Enclosure 2 provides a report from General Electric -Hitachi (GEH) letter,GE-MNGP-AEP-3306, "GEH Response to MELLLA+ EICB RAI," which provides aresponse to the NRC's RAI (Reference 3). Enclosure 2 contains proprietaryinformation.Enclosure 3 provides a non-proprietary copy of the Enclosure 2 RAI response. Thenon-proprietary copy of the RAI response is being provided based on the NRC'sexpectation that the submitter of the proprietary information should provide, if possible,a non-proprietary version of the document with brackets showing where the proprietaryinformation has been deleted.Enclosure 4 provides an affidavit executed to support withholding Enclosure 2 frompublic disclosure. Information in Enclosure 2 contains proprietary information asdefined by 10 CFR 2.390. The affidavit sets forth the basis on which the informationmay be withheld from public disclosure by the NRC and addresses with specificity theconsiderations listed in 10 CFR 2.390(b)(4). Accordingly, NSPM respectfully requeststhat the proprietary information in Enclosure 2 be withheld from public disclosure inaccordance with 10 CFR 2.390(a)4, as authorized by 10 CFR 9.17(a)4.Correspondence with respect to the copyright or proprietary aspects of GEH informationor the supporting GEH affidavit in Enclosure 4 should be addressed to Linda C. Dolan,Manager, Regulatory Compliance, GE-Hitachi Nuclear Energy Americas LLC, 3901Castle Hayne Road, Wilmington, NC 28401. | | |
| Document Control DeskPage 3The supplemental information provided herein does not change the conclusions of theNo Significant Hazards Consideration and the Environmental Consideration evaluationsprovided in Reference 1 for the MELLLA+ license amendment request.In accordance-with 10 CFR 50.91 (b), a copy of this application supplement, withoutenclosures is being provided to the designated Minnesota Official.Summary of CommitmentsThis letter makes no new commitments and no revisions to existing commitments.I declare under penalty of perjury that the foregoing is true and correct.Executed on: Decemberq, 2013Karen D. FiliSite Vice-PresidentMonticello Nuclear Generating PlantNorthern States Power Company-MinnesotaEnclosures (4)cc: Regional Administrator, Region III, USNRC (w/o enclosures)Project Manager, Monticello Nuclear Generating Plant, USNRCResident Inspector, Monticello Nuclear Generating Plant, USNRC (w/oenclosures)Minnesota Department of Commerce (w/o enclosures) | | ==Subject:== |
| }} | | Maximum Extended Load Line Limit Analysis Plus: Cycle 27 Safety Reload Licensing Report and Request for Additional Information Response (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. ML1100280558) |
| | : 2) 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) |
| | : 3) Email from T. Beltz (NRC) to J. Fields (NSPM), "Monticello Nuclear Generating Plant -Draft Request for Additional Information re: Maximum Extended Load Line Limit Analysis Plus LAR Review (TAC No. ME3145)," dated November 26, 2013.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 Specifications (TS). The proposed change would allow operation in the expanded Maximum Extended Load Line Limit Analysis Plus (MELLLA+) |
| | domain. |
| | Document Control Desk Page 2 The purpose of this letter is to provide the NRC with the MNGP cycle 27 Supplemental Reload Licensing Report (SRLR) applicable to MELLLA+ conditions and evaluations and to provide a response to an NRC Request for Additional Information (RAI).Enclosure 1 to this letter provides the MNGP cycle 27 SRLR applicable to MELLLA+conditions and evaluations. |
| | The cycle 27 SRLR is being submitted to the NRC to fulfill the requirements of the MELLLA+ topical report (Reference 2), Limitation and Condition 12.4, which specifies that the SRLR for the initial MELLLA+ implementation cycle shall be submitted for NRC staff confirmation. |
| | The SRLR supports the licensing work performed for the MNGP MELLLA+ license.This reload design was initiated prior to the PRIME transition commitment to utilize PRIME for reload analyses. |
| | The cycle-specific reload analyses are based on GESTR-M, with one exception, and the peak clad temperature (PCT) impact of PRIME was evaluated as part of 10 CFR 50.46 Error Notification 2012-01. The one exception is the Detect and Suppress Solution -Confirmation Density (DSS-CD) Backup Stability Protection (BSP) analysis, which was performed using PRIME. The use of PRIME for the DSS-CD BSP analysis is consistent with NEDO-33173 Supplement 4-A, Rev. 1,"Implementation of PRIME Models and Data in Downstream Methods," November 2012.Enclosure 2 provides a report from General Electric -Hitachi (GEH) letter, GE-MNGP-AEP-3306, "GEH Response to MELLLA+ EICB RAI," which provides a response to the NRC's RAI (Reference 3). Enclosure 2 contains proprietary information. |
| | Enclosure 3 provides a non-proprietary copy of the Enclosure 2 RAI response. |
| | The non-proprietary copy of the RAI response is being provided based on the NRC's expectation that the submitter of the proprietary information should provide, if possible, a non-proprietary version of the document with brackets showing where the proprietary information has been deleted.Enclosure 4 provides an affidavit executed to support withholding Enclosure 2 from public disclosure. |
| | Information in Enclosure 2 contains proprietary information as defined by 10 CFR 2.390. The affidavit sets forth the basis on which the information may be withheld from public disclosure by the NRC and addresses with specificity the considerations listed in 10 CFR 2.390(b)(4). |
| | Accordingly, NSPM respectfully requests that the proprietary information in Enclosure 2 be withheld from public disclosure in accordance with 10 CFR 2.390(a)4, as authorized by 10 CFR 9.17(a)4.Correspondence with respect to the copyright or proprietary aspects of GEH information or the supporting GEH affidavit in Enclosure 4 should be addressed to Linda C. Dolan, Manager, Regulatory Compliance, GE-Hitachi Nuclear Energy Americas LLC, 3901 Castle Hayne Road, Wilmington, NC 28401. |
| | Document Control Desk Page 3 The supplemental information provided herein does not change the conclusions of the No Significant Hazards Consideration and the Environmental Consideration evaluations provided in Reference 1 for the MELLLA+ license amendment request.In accordance-with 10 CFR 50.91 (b), a copy of this application supplement, without enclosures is being provided to the designated Minnesota Official.Summary of Commitments This letter makes no new commitments and no revisions to existing commitments. |
| | I declare under penalty of perjury that the foregoing is true and correct.Executed on: Decemberq, 2013 Karen D. Fili Site Vice-President Monticello Nuclear Generating Plant Northern States Power Company-Minnesota Enclosures (4)cc: Regional Administrator, Region III, 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)}} |
Letter Sequence Request |
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TAC:ME3145, Clarify Application of Setpoint Methodology for LSSS Functions (Approved, Closed) |
Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance, Acceptance
- Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement
Administration
- Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance
- Meeting, Meeting, Meeting, Meeting, Meeting, Meeting
Results
Other: L-MT-08-091, Calculation 0801040.301, Steam Dryer Outer Hood Submodel Analysis., L-MT-09-002, Response to NRC Probabilistic Risk Assessment (PRA) Branch Requests for Additional Information (Rais) Dated December 5, 2008, L-MT-09-003, Response to NRC Environmental Branch Requests for Additional Information (Rais) Dated December 18, 2008, L-MT-09-004, Enclosure 1 (Continued) to L-MT-09-004, NSPM Response to Containment & Ventilation Branch RAI Number 2, Copy of MNGP Appr T0406 Data Transmittal Pages 1 of 538 Through Pages 538 of 538, L-MT-09-026, Calculation 0000-0081-6958 MNGP-PRNMS-APRM Calc-2008-NP, Rev. 1, Average Power Range Monitor Selected Prnm Licensing Setpoints - EPU Operation (Numac), L-MT-09-027, Extended Power Uprate: Response to Instrumentation and Controls Branch RAI No. 3 Dated April 6, 2009, L-MT-09-044, Extended Power Uprate: Response to NRC Mechanical and Civil Engineering Review Branch (Emcb) Requests for Additional Information (Rais) Dated March 28, 2009, L-MT-09-049, Drawing C.5-2007, Revision 15, Failure to Scram, L-MT-09-073, Extended Power Uprate: Response to NRC Containment and Ventilation Review Branch (Scvb) Requests for Additional Information (Rais) Dated July 2, 2009 and July 14, 2009, L-MT-09-083, Extended Power Uprate: Limit Curves Requested by the Mechanical and Civil Review Branch (Emcb) Associated with Requests for Additional Information (Rais) Dated March 20, 2009, L-MT-09-088, Extended Power Uprate: Revision to Clarify Text in Enclosures 5 and 7 of L-MT-08-052, L-MT-09-097, Extended Power Uprate: Acknowledgement of NRC Review Delay, L-MT-10-025, Extended Power Uprate (Epu): Response to NRC-NSPM February 25, 2010 Conference Call, L-MT-10-072, Extended Power Uprate: Updates to Docketed Information, L-MT-11-044, Uprate (Epu): Update on EPU Commitments, L-MT-12-056, WCAP-17549-NP, Rev. 0, Monticello Replacement Steam Dryer Structural Evaluation for High-Cycle Acoustic Loads Using ACE, L-MT-12-090, Westinghouse, LTR-A&SA-12-8, Rev. 1, Attachment B, Recommendations for Inspections of the Monticello Replacement Steam Dryer., L-MT-12-114, Drawing C.5-2007, Rev. 17, Failure to Scram, L-MT-13-020, Enclosure 1 - Responses to the Gap Analysis, L-MT-13-029, Enclosure 14 to L-MT-13-029 - WCAP-17716-NP, Revision 0, Benchmarking of the Acoustic Circuit Enhanced Revision 2.0 for the Monticello Steam Dryer Replacement Project., L-MT-13-091, WCAP-17716-NP, Revision 1 - Benchmarking of the Acoustic Circuit Enhanced Revision 2.0 for the Monticello Steam Dryer Replacement Project, Enclosure 14, L-MT-13-092, Extended Power Uprate (Epu): Completion of EPU Commitments, Proposed License Conditions and Revised Power Ascension Test Plan, L-MT-13-096, GE-MNGP-AEP-3304R1, Enclosure 4, NEDC-33435 Corrected Pages, L-MT-13-126, Enclosure 3, GE-MNGP-AEP-3306, Enclosure 2 GEH Response to Mella+ Eicb RAI and Affidavit, L-MT-14-023, Maximum Extended Load Line Limit Analysis Plus: Technical Specification Clarifications, L-MT-15-074, Enclosure 7, WCAP-18604-NP, Revision 0, Monticello EPU Main Steam Line Strain Data Evaluation Report., L-MT-16-017, Revised Commitment to Reconcile Analysis of Bypass Voiding for Transition to Areva Analysis Methodology, L-MT-16-071, Submittal of 2016 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46, ML083230111, ML083400402, ML083500575, ML083570610, ML083590127, ML090710680, ML090710683, ML090710684, ML091120578, ML091140470, ML091410121, ML091410122, ML091410123, ML091410124, ML091760769, ML092290250, ML092810554, ML093160816, ML093220925, ML093220964, ML093620024, ML100280558... further results
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MONTHYEARML0907106832008-02-17017 February 2008 Enclosure 1 (Continued) to L-MT-09-004, NSPM Response to Containment & Ventilation Branch RAI Number 2, Attachment 1-1g Through End of Encl. 1 Project stage: Other ML13064A4352008-03-20020 March 2008 CA-95-075, Main Steam Line High Flow Setpoint, Attachment 4 Project stage: Other ML0914101242008-08-11011 August 2008 Monticello - Calculation CA-08-050, Rev. 0, Instrument Setpoint Calculation - Average Power Range Monitor (APRM) Non-Flow Eiased Prnm Setpoints for Cl Tp and EPU Project stage: Other L-MT-08-091, Calculation 0801040.301, Steam Dryer Outer Hood Submodel Analysis.2008-10-31031 October 2008 Calculation 0801040.301, Steam Dryer Outer Hood Submodel Analysis. Project stage: Other ML0832301122008-10-31031 October 2008 NEDC-33322-NP, Revision 3, Monticello Nuclear Generating Plant, Safety Analysis Report, Constant Pressure Power Uprate. Project stage: Request ML0832301112008-11-0505 November 2008 Monticello Nuclear Generating Plant, License Amendment Request: Extended Power Uprate Project stage: Other ML0832301142008-11-0505 November 2008 Monticello Nuclear Generating Plant, Steam Dryer Dynamic Stress Evaluation. Project stage: Request ML0834003662008-12-0202 December 2008 Extended Power Uprate Acceptance Review Questions on Probabilistic Risk Assessment Issues Project stage: Acceptance Review ML0834004022008-12-0505 December 2008 Extended Power Uprate - Monticello - Request to Supplement the Application in the Probabilistic Risk Assessment Area Project stage: Other ML0835000992008-12-11011 December 2008 Monticello Extended Power Uprate (Usnrc TAC MD9990): Acceptance Review Supplement Regarding Steam Dryer Outer Hood Submodel Analysis Project stage: Supplement ML0835303022008-12-16016 December 2008 Draft Request for Additional Information, Environmental Issues of EPU Application Project stage: Draft RAI ML0936200242008-12-18018 December 2008 Report 0800760.401, Rev. 1, Flaw Evaluation and Vibration Assessment of Existing Monticello Steam Dryer Flaws for Extended Power Uprate. Project stage: Other ML0835005752008-12-18018 December 2008 Letter Finding 11/5/08 Application for Amendment Acceptable for Review Project stage: Other ML0835309982008-12-18018 December 2008 EPU Application - Additional RAI Question Regarding an Environmental Issue Project stage: RAI ML0835310022008-12-18018 December 2008 Proposed Eou Amendment - Revised RAI Re. Containment Analysis Project stage: RAI ML0914101222008-12-18018 December 2008 Monticello - Calculation CA-95-075, Revision 1, Main Steam Line High Flow Setpoint Project stage: Other ML0914101212008-12-19019 December 2008 Monticello - Calculation CA-95-073, Revision 4, Reactor Low Water Level SCRAM Setpoint Project stage: Other ML0835901272009-01-14014 January 2009 Letter Conveying Determination That Enclosure 5 of 11/5/08 Application for EPU Amendment Contains Proprietary Information and Withheld from Public Disclosure Project stage: Other ML0835706102009-01-26026 January 2009 Letter Conveying Determination That Enclosure 11 of 11/5/08 Application for EPU Amendment Contains Proprietary Information and Is Withheld from Public Disclosure Project stage: Other L-MT-09-003, Response to NRC Environmental Branch Requests for Additional Information (Rais) Dated December 18, 20082009-01-29029 January 2009 Response to NRC Environmental Branch Requests for Additional Information (Rais) Dated December 18, 2008 Project stage: Other L-MT-09-005, Revision to Attachment 1 of Enclosure 17 of MNGP License Amendment Request for Extended Power Uprate2009-02-0404 February 2009 Revision to Attachment 1 of Enclosure 17 of MNGP License Amendment Request for Extended Power Uprate Project stage: Request L-MT-09-002, Response to NRC Probabilistic Risk Assessment (PRA) Branch Requests for Additional Information (Rais) Dated December 5, 20082009-02-0404 February 2009 Response to NRC Probabilistic Risk Assessment (PRA) Branch Requests for Additional Information (Rais) Dated December 5, 2008 Project stage: Other ML0904204852009-02-11011 February 2009 Draft RAI from Materials Engineering Re. Proposed Extended Power Uprate Amendment Project stage: Draft RAI ML0907106792009-02-17017 February 2009 Monticello, Response to NRC Containment & Ventilation Branch Request for Additional Information (Rals) Dated December 18, 2008 Project stage: Request ML0907106802009-02-17017 February 2009 Monticello, Enclosure 1 to L-MT-09-004, NSPM Response to Containment & Ventilation Branch RAI Number 1 Dated December 18, 2008, Cover Through Copy of MNGP Appr T0406 Data Transmittal Page 424 of 424 Project stage: Other L-MT-09-004, Enclosure 1 (Continued) to L-MT-09-004, NSPM Response to Containment & Ventilation Branch RAI Number 2, Copy of MNGP Appr T0406 Data Transmittal Pages 1 of 538 Through Pages 538 of 5382009-02-17017 February 2009 Enclosure 1 (Continued) to L-MT-09-004, NSPM Response to Containment & Ventilation Branch RAI Number 2, Copy of MNGP Appr T0406 Data Transmittal Pages 1 of 538 Through Pages 538 of 538 Project stage: Other ML0907106842009-02-17017 February 2009 Enclosures 2 - 4: NSPM Response to Containment & Ventilation Branch RAI Numbers 2, 3 and 4 Dated December 18, 2008 Project stage: Other L-MT-09-018, Response to NRC Steam Generator Tube Integrity & Chemical Engineering Branch Request for Additional Information (RAI) Dated February 11, 20092009-02-24024 February 2009 Response to NRC Steam Generator Tube Integrity & Chemical Engineering Branch Request for Additional Information (RAI) Dated February 11, 2009 Project stage: Request ML0907100912009-03-11011 March 2009 Conveying Draft RAI Questions from the Instrumentation and Controls Branch Regarding the Proposed Extended Power Uprate Amendment Project stage: Draft RAI ML0907200572009-03-12012 March 2009 Conveys Draft RAI Regarding Fire Protection for the Proposed Extended Power Uprate Amendment Project stage: Draft RAI ML0907800062009-03-18018 March 2009 Draft RAI from Probabilistic Risk Assessment Licensing Branch on the Proposed Extended Power Uprate Amendment Project stage: Draft RAI ML0907800042009-03-18018 March 2009 Conveys Draft RAI by the PRA Licensing Branch on the Proposed EPU Amendment Project stage: Draft RAI ML0907809032009-03-19019 March 2009 Conveys Draft RAI Provided by the Containment and Ventilation Branch on the Proposed Extended Power Uprate Amendment Project stage: Draft RAI ML0907809092009-03-19019 March 2009 RAI from the Containment and Ventilation Branch the Proposed Extended Power Uprate Amendment Project stage: RAI L-MT-09-017, Extended Power Uprate: Response to NRC Reactor Systems Branch & Nuclear Performance & Code Review Branch Request for Additional Information (RAI) Dated January 16, 20092009-03-19019 March 2009 Extended Power Uprate: Response to NRC Reactor Systems Branch & Nuclear Performance & Code Review Branch Request for Additional Information (RAI) Dated January 16, 2009 Project stage: Request ML0908200312009-03-20020 March 2009 Draft RAI Re. Health Physics Issues for the Proposed Extended Power Uprate Amendment Project stage: Draft RAI ML0908200992009-03-23023 March 2009 Draft RAI from the Balance of Plant Branch Re the Proposed Amendment on Extended Power Uprate Project stage: Draft RAI ML0908800022009-03-28028 March 2009 Second Portion of Draft RAI from the Mechanical and Civil Engineering Branch Regarding the Proposed Extended Power Uprate Amendment Project stage: Draft RAI ML0908800032009-03-28028 March 2009 Draft RAI from the Electrical Engineering Branch Re. the Proposed Extended Power Uprate Amendment for Monticello Project stage: Draft RAI ML0908800012009-03-29029 March 2009 Additional Draft RAI Questions from the Containment and Ventilation Branch Proposed EPU Amendment for Monticello Project stage: Draft RAI 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
MONTHYEARML24025A9362024-01-31031 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0055 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) IR 05000263/20230042024-01-31031 January 2024 Integrated Inspection Report 05000263/2023004 ML24024A0722024-01-24024 January 2024 Independent Spent Fuel Storage Installation, Onticello, Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000263/20244012024-01-22022 January 2024 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000263/2024401 L-MT-23-054, Subsequent License Renewal Application Supplement 82024-01-11011 January 2024 Subsequent License Renewal Application Supplement 8 L-MT-23-047, License Amendment Request: Revision to the MNGP Pressure Temperature Limits Report to Change the Neutron Fluence Methodology and Incorporate New Surveillance Capsule Data2023-12-29029 December 2023 License Amendment Request: Revision to the MNGP Pressure Temperature Limits Report to Change the Neutron Fluence Methodology and Incorporate New Surveillance Capsule Data L-MT-23-056, Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 1 Part 22023-12-18018 December 2023 Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 1 Part 2 ML23349A0572023-12-15015 December 2023 and Independent Spent Fuel Storage Installation, Revision to Correspondence Service List for Northern States Power - Minnesota IR 05000263/20234022023-12-13013 December 2023 Security Baseline Inspection Report 05000263/2023402 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 ML23319A3182023-11-15015 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000263/20230032023-11-13013 November 2023 Integrated Inspection Report 05000263/2023003 and 07200058/2023001 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 ML23291A1102023-10-23023 October 2023 Environmental Audit Summary and RCIs and RAIs ML23285A3062023-10-12012 October 2023 Implementation of the Fleet Standard Emergency Plan for the Monticello Nuclear Generating Plant and the Prairie Island Nuclear Generating Plant 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 ML23262B0372023-09-19019 September 2023 Response to NRC Request for Additional Information Regarding the 2023 Monticello and Prairie Island Plant Decommissioning Funding Status Reports ML23248A2092023-09-18018 September 2023 Proposed Alternative VR-11 to the Requirements of the ASME OM Code Associated with Periodic Verification Testing of MO-2397, Reactor Water Cleanup Inboard Isolation Valve ML23256A1682023-09-13013 September 2023 Independent Spent Fuel Storage Installation and Monticello Nuclear Generating Plant - Voluntary Security Clearance Program 2023 Insider Threat Program Self-Inspection IR 05000263/20230102023-09-0707 September 2023 Commercial Grade Dedication Inspection Report 05000263/2023010 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 ML23214A2412023-08-31031 August 2023 Letter: Aging Management Audit - Monticello Unit 1 - Subsequent License Renewal Application IR 05000263/20230052023-08-30030 August 2023 Updated Inspection Plan for Monticello Nuclear Generating Plant (Report 05000263/2023005) L-MT-23-035, Subsequent License Renewal Application Supplement 52023-08-28028 August 2023 Subsequent License Renewal Application Supplement 5 ML23241A9732023-08-21021 August 2023 Request for Scoping Comments Concerning the Environmental Review of Monticello Nuclear Generating Plant, Unit 1, Subsequent License Renewal Application (Docket No. 50-263) 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 ML23222A0122023-08-10010 August 2023 Independent Spent Fuel Storage Installation and Monticello Nuclear Generating Plant - Changes in Foreign Ownership, Control or Influence ML23215A1312023-08-0909 August 2023 License Renewal Regulatory Audit Regarding the Environmental Review of the Subsequent License Renewal Application IR 05000263/20230022023-08-0707 August 2023 Plantintegrated Inspection Report 05000263/2023002 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 ML23198A0412023-07-28028 July 2023 LRA Availability Letter ML23206A2342023-07-25025 July 2023 Independent Spent Fuel Storage Installation, and Monticello Nuclear Generating Plant, Changes in Foreign Ownership, Control or Influence ML23201A0352023-07-24024 July 2023 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information ML23202A0032023-07-21021 July 2023 Independent Spent Fuel and Independent Spent Fuel Storage Installation, Monticello Nuclear Generating Plant, Submittal of Quality Assurance Topical Report (NSPM-1) 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 ML23195A1732023-07-14014 July 2023 Revision of Standard Practice Procedures Plan IR 05000263/20235012023-07-13013 July 2023 Emergency Preparedness Inspection Report 05000263/2023501 2024-01-31
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@XcelEnergy Monticello Nuclear Generating Plant 2807 W County Rd 75 Monticello, MN 55362 December 20, 2013 L-MT-1 3-126 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:
Maximum Extended Load Line Limit Analysis Plus: Cycle 27 Safety Reload Licensing Report and Request for Additional Information Response (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. ML1100280558)
- 2) 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)
- 3) Email from T. Beltz (NRC) to J. Fields (NSPM), "Monticello Nuclear Generating Plant -Draft Request for Additional Information re: Maximum Extended Load Line Limit Analysis Plus LAR Review (TAC No. ME3145)," dated November 26, 2013.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 Specifications (TS). The proposed change would allow operation in the expanded Maximum Extended Load Line Limit Analysis Plus (MELLLA+)
domain.
Document Control Desk Page 2 The purpose of this letter is to provide the NRC with the MNGP cycle 27 Supplemental Reload Licensing Report (SRLR) applicable to MELLLA+ conditions and evaluations and to provide a response to an NRC Request for Additional Information (RAI).Enclosure 1 to this letter provides the MNGP cycle 27 SRLR applicable to MELLLA+conditions and evaluations.
The cycle 27 SRLR is being submitted to the NRC to fulfill the requirements of the MELLLA+ topical report (Reference 2), Limitation and Condition 12.4, which specifies that the SRLR for the initial MELLLA+ implementation cycle shall be submitted for NRC staff confirmation.
The SRLR supports the licensing work performed for the MNGP MELLLA+ license.This reload design was initiated prior to the PRIME transition commitment to utilize PRIME for reload analyses.
The cycle-specific reload analyses are based on GESTR-M, with one exception, and the peak clad temperature (PCT) impact of PRIME was evaluated as part of 10 CFR 50.46 Error Notification 2012-01. The one exception is the Detect and Suppress Solution -Confirmation Density (DSS-CD) Backup Stability Protection (BSP) analysis, which was performed using PRIME. The use of PRIME for the DSS-CD BSP analysis is consistent with NEDO-33173 Supplement 4-A, Rev. 1,"Implementation of PRIME Models and Data in Downstream Methods," November 2012.Enclosure 2 provides a report from General Electric -Hitachi (GEH) letter, GE-MNGP-AEP-3306, "GEH Response to MELLLA+ EICB RAI," which provides a response to the NRC's RAI (Reference 3). Enclosure 2 contains proprietary information.
Enclosure 3 provides a non-proprietary copy of the Enclosure 2 RAI response.
The non-proprietary copy of the RAI response is being provided based on the NRC's expectation that the submitter of the proprietary information should provide, if possible, a non-proprietary version of the document with brackets showing where the proprietary information has been deleted.Enclosure 4 provides an affidavit executed to support withholding Enclosure 2 from public disclosure.
Information in Enclosure 2 contains proprietary information as defined by 10 CFR 2.390. The affidavit sets forth the basis on which the information may be withheld from public disclosure by the NRC and addresses with specificity the considerations listed in 10 CFR 2.390(b)(4).
Accordingly, NSPM respectfully requests that the proprietary information in Enclosure 2 be withheld from public disclosure in accordance with 10 CFR 2.390(a)4, as authorized by 10 CFR 9.17(a)4.Correspondence with respect to the copyright or proprietary aspects of GEH information or the supporting GEH affidavit in Enclosure 4 should be addressed to Linda C. Dolan, Manager, Regulatory Compliance, GE-Hitachi Nuclear Energy Americas LLC, 3901 Castle Hayne Road, Wilmington, NC 28401.
Document Control Desk Page 3 The supplemental information provided herein does not change the conclusions of the No Significant Hazards Consideration and the Environmental Consideration evaluations provided in Reference 1 for the MELLLA+ license amendment request.In accordance-with 10 CFR 50.91 (b), a copy of this application supplement, without enclosures is being provided to the designated Minnesota Official.Summary of Commitments This letter makes no new commitments and no revisions to existing commitments.
I declare under penalty of perjury that the foregoing is true and correct.Executed on: Decemberq, 2013 Karen D. Fili Site Vice-President Monticello Nuclear Generating Plant Northern States Power Company-Minnesota Enclosures (4)cc: Regional Administrator, Region III, 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)