|
|
Line 19: |
Line 19: |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:REGuZq UNITED STA"'°11... NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 << 0 \n . : 0 V";. b Decem er 13, 2012 >t***i< Northern States Power Company of Minnesota FACILITYMonticello Nuclear Generating Plant SUMMARY OF THE NOVEMBER 20, 2012, PUBLIC MEETING WITH NORTHERN STATES POWER COMPANY OF MINNESOTA TO DISCUSS THE EXTENDED POWER UPRATE GAP ANALYSIS (TAC NO. MD9990) On November 20, 2012, the U.S. Nuclear Regulatory Commission (NRC) staff held a Category 1 public meeting with representatives of Northern States Power Company of Minnesota, doing business as Xcel Energy, at NRC headquarters. The purpose of the meeting was for the licensee to present the results of its extended power uprate (EPU) gap analysis. The gap analysis identifies changes to information previously submitted to the NRC in the EPU license amendment request (LAR) application and supplements. The enclosure to this summary contains the list of participants. The licensee introduced its EPU gap analysis in a slide presentation (docketed at Agencywide Documents Access and Management System (ADAMS) Accession No. ML 12335A173). The presentation summarized the history and current status of the Monticello EPU review, and provided the methodology for how the gap analysis results were identified and dispositioned. The focus of the meeting was a discussion of the gap analysis results, which Xcel Energy summarized in a table (docketed at ADAMS Accession No. ML 12335A176). The NRC staff questioned the licensee on various aspects of the table and provided the following comments listed below: Topic NRC Staff Comment(s) on Proposed Disposition | | {{#Wiki_filter:REG uZq UNITE D ST A |
| | "'°11... NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 |
| | << 0 \n . : 0 V";. b Decem er 13, 2012 >t***i< |
| | Northern States Power Company of Minnesota FACILITYMonticello Nuclear Generating Plant |
| | |
| | ==SUMMARY== |
| | OF THE NOVEMBER 20, 2012 , PUBLIC MEETING WITH NORTHERN STATES POWER COMPANY OF MINNESOTA TO DISCUSS THE EXTENDED POWER UPRATE GAP ANALYSIS (TAC NO. MD9990) On November 20 , 2012, the U.S. Nuclear Regulatory Commission (NRC) staff held a Category 1 public meeting with representatives of Northern States Power Company of Minnesota, doing business as Xcel Energy, at NRC headquarters. |
| | The purpose of the meeting was for the licensee to present the results of its extended power uprate (EPU) gap analysis. The gap analysis identifies changes to information previously submitted to the NRC in the EPU license amendment request (LAR) application and supplements. |
| | The enclosure to this summary contains the list of participants. |
| | The licensee introduced its EPU gap analysis in a slide presentation (docketed at Agencywide Documents Access and Management System (ADAMS) Accession No. ML 12335A173). The presentation summarized the history and current status of the Monticello EPU review , and provided the methodology for how the gap analysis results were identified and dispositioned. The focus of the meeting was a discussion of the gap analysis results, which Xcel Energy summarized in a table (docketed at ADAMS Accession No. ML 12335A176). The NRC staff questioned the licensee on various aspects of the table and provided the following comments listed below: Topic NRC Staff Comment(s) on Proposed Disposition |
| * Identify the ten MOVs Motor-Operated Valves | | * Identify the ten MOVs Motor-Operated Valves |
| * Identify the impact on functional performance (MOVs) | | * Identify the impact on functional performance (MOVs) |
| * Discuss compliance with generic guidance | | * Discuss compliance with generic guidance |
| * Discuss remaining in compliance with 10 CFR 50 .55(a) Grid Stability | | * Discuss remaining in compliance with 10 CFR 50 .55(a) Grid Stabil i ty |
| * Staff requests MISO [Midwest Independent Transmission Assessment System Operator] letter be provided for review Environmental | | * Staff requests MISO [Midwest Independent Transmission Assessment System Operator] |
| | letter be provided for review Environmental |
| * Staff requests a discussion of the changes and to provide Qualification (EQ) validation of EQ parameters Battery Capacity | | * Staff requests a discussion of the changes and to provide Qualification (EQ) validation of EQ parameters Battery Capacity |
| * No specific comments | | * No specific comments |
| -2 NRC Staff Comment(s) on Proposed Disposition Topic Staff understands that General Electric -Hitachi (GEH) is working on revising this calculation related to possible Main Steam Line High changes to choke flow rates Flow Trip Staff requests changes, when available, to be submitted for review Staff indicates a potential for follow-up discussions As long as changes are administrative in nature (i.e., results of calculations are unaffected), a brief description of Changes to Calculations the changes submitted on the docket should be sufficient If set point values are affected, then the staff requests the updated calculation be submitted for review Steam Dryer No specific comments Reactor Water Cleanup Staff requests that information related to change beImpact on Reactor Water submitted for review Quality EPU LAR for Pressure-Temperature Limits | | -2 NRC Staff Comment(s) on Proposed Disposition Topic Staff understands that General Electric -Hitachi (GEH) is working on revising this calculation related to possible Main Steam Line High changes to choke flow rates Flow Trip Staff requests changes, when available, to be submitted for review Staff indicates a potential for follow-up discussions As long as changes are administrative in nature (i.e., results of calculations are unaffected), a brief description of Changes to Calculations the changes submitted on the docket should be sufficient If set point values are affected, then the staff requests the updated calculation be submitted for review Steam Dryer No specific comments Reactor Water Cleanup Staff requests that information related to change be Impact on Reactor Water submitted for review Quality EPU LAR for Pressure-Temperature Limits |
| * No specific comments LAR Staff requests verification that offsite dose still meets the limits of 40 CFR 190 with the addition of hydrogen water Noble Metals chemistry and noble metal injection Modification Licensee informed that there may be follow-up requests for additional information from NRC staff Abnormal Operating Staff requests information regarding the AOP change if the Procedure (AOP) turbine backpressure limit is changedChange Energy Core Cooling System (ECCS) Pump No specific comments Flow Rates Residual Heat Removal Core Spray Pump Room No specific comments Post-Loss-of-Coolant Accident Heatup Final Feedwater | | * No specific comments LAR Staff requests verification that offsite dose still meets the limits of 40 CFR 190 with the addition of hydrogen water Noble Metals chemistry and noble metal injection Modification Licensee informed that there may be follow-up requests for additional information from NRC staff Abnormal Operating Staff requests information regarding the AOP change if the Procedure (AOP) turbine backpressure limit is changed Change Energy Core Cooling System (ECCS) Pump No specific comments Flow Rates Residual Heat Removal Core Spray Pump Room No specific comments Post-Loss-of-Coolant Accident Heatup Final Feedwater |
| * Staff commented on how GEH evaluated the effect of the Temperature change | | * Staff commented on how GEH evaluated the effect of the Temperature change |
| -3 TODic NRC Staff Comment(s) on Proposed Disposition Piping Components Requiring Further Analysis | | -3 TODic NRC Staff Comment(s) on Proposed Disposition Piping Components Requiring Further Analysis |
Line 48: |
Line 58: |
| -4 NRC Staff Comment(s) on Proposed Disposition Togic Reactor Head Spray Nozzle Fatigue | | -4 NRC Staff Comment(s) on Proposed Disposition Togic Reactor Head Spray Nozzle Fatigue |
| * No specific comments Assessment Emergency Operating Plan (EOP) Flow Chart Staff requests a copy of the EOP flowchart for ATWS for Anticipated Transfer Without Scram (A TWS) Avoidance of Trip of Both No specific comments, other than the staff will want to know Reactor Feed Pumps on if there is a commitment change Transients Staff indicates that information of what was reviewed to reach the conclusion that there are on impacts to the EA Environmental needs to be submitted and placed on the docket Assessment (EA) Staff recommends that the applicant refer to 10 CFR 50.92 when submitting changes list of Modifications | | * No specific comments Assessment Emergency Operating Plan (EOP) Flow Chart Staff requests a copy of the EOP flowchart for ATWS for Anticipated Transfer Without Scram (A TWS) Avoidance of Trip of Both No specific comments, other than the staff will want to know Reactor Feed Pumps on if there is a commitment change Transients Staff indicates that information of what was reviewed to reach the conclusion that there are on impacts to the EA Environmental needs to be submitted and placed on the docket Assessment (EA) Staff recommends that the applicant refer to 10 CFR 50.92 when submitting changes list of Modifications |
| * No specific comments Required Provide a supplemental reload licensing report Provide an ECCS evaluation Staff requests a detailed discussion of changes to electrical equipment loading and capacities since the last submittal, Other NRC Staff including diesel generators Requests If Part 21 related to loss of stator cooling affects rvlNGP, provide an analytical assessment Staff requests review of RIS 2008-30 for applicability to MGNP Members of the public participated by telephone. No portion of this meeting was closed to the public because no proprietary information or security-related information was discussed by the participants. Before the meeting adjourned, all participants were given the opportunity to comment on any aspects of the meeting. No comment or feedback was provided. | | * No specific comments Required Provide a supplemental reload licensing report Provide an ECCS evaluation Staff requests a detailed discussion of changes to electrical equipment loading and capacities since the last submittal, Other NRC Staff including diesel generators Requests If Part 21 related to loss of stator cooling affects rvlNGP, provide an analytical assessment Staff requests review of RIS 2008-30 for applicability to MGNP Members of the public participated by telephone. |
| -Please direct any inquiries to me at 301-415-3049 or e-mail terry.beltz@nrc.gov. Terry A. Beltz, Senior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket 1\10. 50-263 | | No portion of this meeting was closed to the public because no proprietary information or security-related information was discussed by the participants. Before the meeting adjourned, all participants were given the opportunity to comment on any aspects of the meeting. No comment or feedback was provided. |
| | -Please direct any inquiries to me at 301-415-3049 or e-mail terry.beltz@nrc |
| | .gov. Terry A. Beltz, Senior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket 1\10. 50-263 |
|
| |
|
| ==Enclosure:== | | ==Enclosure:== |
| List of Participants cc w/encl: Distribution via ListServ LIST OF MEETING BETWEEN THE U.S. NUCLEAR REGULATORY AND NORTHERN STATES POWER COMPANY OF MONTICELLO NUCLEAR GENERATING EXTENDED POWER UPRATE GAP ANALYSIS NOVEMBER NAME ORGANIZATION Briana Balsam f\I RC/NRR/DLR/RERB Chakrapani Basavaratu N RC/NRR/DE/EMCB Terry Beltz NRC/NRR/DORLlLPL3-1 William Bentley ** TVA Joel Beres IVlNGP John Bjorseth Xcel Energy Kevin Borton Exelon Robert Carlson N RC/N RR/DORLlLPL3-1 William Cheever ** MNGP Nicholas DiFrancesco N RC/N RR/DORLlLPL3-2 DyLanne Duvigneaud NRC/NRR/DRNAADB Gene Eckholt Xcel Energy Steve Frankl NRC/RES/DSNRSAB Peter Glass ** Xcel Energy Steve Hammer ** MNGP Nathan Haskell Xcel Energy Denzel Housley ** TVA Naeem Iqbal NRC/NRR/DRNAFPB Chris Jackson NRC/NRR/DSS/SRXB William Jessup N RC/NRRIDE/EMCB Steve Jones NRC/f\lRR/DSS/SBPB Aziz Khanifar Xcel Energy Michelle Kichline NRC/NRR/DRNAADB Jeff Kitsembel ** State of Wisconsin George Lapinsky ** NRC/NRRIDRNAHPB Nancy Martinez NRC/NRR/DLR/RERB Matthew McConnell NRC/NRR/DE/EEEB Tony McMurtray NRC/NRR/DE/EPTB Tim Mossman NRC/NRR/DE/EICB Marty Murphy I\JRC/NRR/DE/EMCB Ivy Netzel ** Performance Power Systems Aloysius Obodoako NRC/NRR/DE/ESGB John Osborne ** TVA (Browns Ferry) Ben Parks ** N RC/N RR/DSS/SRXB Jigar Patel NRC/NRR/DRNAPLA Enclosure LIST OF PARTICIPANTS (continued) NAME Roger Pedersen Dave Pennington ** Ahsan Sallman Travis Tate Jeff Tollefson ** Alexander Tsirigotis ** Participated by telephone ORGANIZATION NRC/NRRIDRAlAHPB MNGP N R CIt\! R RIDSS/SCVB I'J RC/NRRIDRAIMDB MNGP NRC/NRRIDE/EMCB Acronyms for List of Participants MDB AFPB AHPB APLA DE DLR DORL DRA DSS EEEB EICB EMCB ESGB EPTB LPL3-1 LPL3-2 rvlNGP NRC NRR RERB RES SBPB SCVB SRXB TVA Accident Dose Branch Fire Protection Branch Health Physics & Human Performance Branch PRA Licensing Branch Division of Engineering Division of License Renewal Division of Operating Reactor Licensing Division of Risk Assessment Division of Safety Systems Electrical Engineering Branch Instrumentation and Controls Branch Mechanical & Civil Engineering Branch Steam Generator Tube Integrity & Chemical Engineering Branch Component Performance & Testing Branch Plant Licensing Branch 111-1 Plant Licensing Branch 111-2 Monticello Nuclear Generating Plant U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Environmental Review & Guidance Update Branch Office of Nuclear Research Balance-of-Plant Branch Containment and Ventilation Branch Reactor Systems Branch Tennessee Valley Authority | | List of Participants cc w/encl: Distribution via ListServ LIST OF MEETING BETWEEN THE U.S. NUCLEAR REGULATORY AND NORTHERN STATES POWER COMPANY OF MONTICELLO NUCLEAR GENERATING EXTENDED POWER UPRATE GAP ANALYSIS NOVEMBER NAME ORGANIZATION Briana Balsam f\I RC/NRR/DLR/RERB Chakrapani Basavaratu N RC/NRR/DE/EMCB Terry Beltz NRC/NRR/DORLlLPL3-1 William Bentley ** TVA Joel Beres IVlNGP John Bjorseth Xcel Energy Kevin Borton Exelon Robert Carlson N RC/N RR/DORLlLPL3-1 William Cheever ** MNGP Nicholas DiFrancesco N RC/N RR/DORLlLPL3-2 DyLanne Duvigneaud NRC/NRR/DRNAADB Gene Eckholt Xcel Energy Steve Frankl NRC/RES/DSNRSAB Peter Glass ** Xcel Energy Steve Hammer ** MNGP Nathan Haskell Xcel Energy Denzel Housley ** TVA Naeem Iqbal NRC/NRR/DRNAFPB Chris Jackson NRC/NRR/DSS/SRXB William Jessup N RC/NRRIDE/EMCB Steve Jones NRC/f\lRR/DSS/SBPB Aziz Khanifar Xcel Energy Michelle Kichline NRC/NRR/DRNAADB Jeff Kitsembel |
| -5 Please direct any inquiries to me at 301-415-3049 or e-mail terry.beltz@nrc.gov. Terry A. Beltz, Senior Project Manager IRAJ Plant Licensing Branch"1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-263 | | ** State of Wisconsin George Lapinsky ** NRC/NRRIDRNAHPB Nancy Martinez NRC/NRR/DLR/RERB Matthew McConnell NRC/NRR/DE/EEEB Tony McMurtray NRC/NRR/DE/EPTB Tim Mossman NRC/NRR/DE/EICB Marty Murphy I\JRC/NRR/DE/EMCB Ivy Netzel ** Performance Power Systems Aloysius Obodoako NRC/NRR/DE/ESGB John Osborne ** TV A (Browns Ferry) Ben Parks ** N RC/N RR/DSS/SRXB Jigar Patel NRC/NRR/DRNAPLA Enclosure LIST OF PARTICIPANTS (continued) |
| | NAME Roger Pedersen Dave Pennington |
| | ** Ahsan Sallman Travis Tate Jeff Tollefson |
| | ** Alexander Tsirigotis |
| | ** Participated by telephone ORGANIZATION NRC/NRRIDRAlAHPB MNGP N R CIt\! R RIDSS/SCVB I'J RC/NRRIDRAI MDB MNGP NRC/NRRIDE/EMCB Acronyms for List of Participants MDB AFPB AHPB APLA DE DLR DORL DRA DSS EEEB EICB EMCB ESGB EPTB LPL3-1 LPL3-2 rvlNGP NRC NRR RERB RES SBPB SCVB SRXB TVA Accident Dose Branch Fire Protection Branch Health Physics & Human Performance Branch PRA Licensing Branch Division of Engineering Division of License Renewal Division of Operating Reactor Licensing Division of Risk Assessment Division of Safety Systems Electrical Engineering Branch Instrumentation and Controls Branch Mechanical |
| | & Civil Engineering Branch Steam Generator Tube Integrity |
| | & Chemical Engineering Branch Component Performance |
| | & Testing Branch Plant Licensing Branch 111-1 Plant Licensing Branch 111-2 Monticello Nuclear Generating Plant U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Environmental Review & Guidance Update Branch Office of Nuclear Research Balance-of-Plant Branch Containment and Ventilation Branch Reactor Systems Branch Tennessee Valley Authority |
| | -5 Please direct any inquiries to me at 301-415-3049 or e-mail terry.beltz@nrc.gov. Terry A. Beltz , Senior Project Manager IRAJ Plant Licensing Branch" 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-263 |
|
| |
|
| ==Enclosure:== | | ==Enclosure:== |
| List of Participants cc w/encl: Distribution via ListServ DISTRIBUTION : PUBLIC LPL3-1 R/F BBalsam, NRR MMcConnell, NRR RidsAcrsAcnw_MailCTR Resource CBasavaratu, NRR AMcMurtray, NRR RidsNrrDorlLpl3-1 Resource DDuvigneaud, NRR TMossman, NRR RidsNrrLASRohrer Resource Nlqbal, NRR MMurphy, NRR RidsNrrPMMonticelio Resource CJackson, NRR AObodoako, NRR RidsRgn3MailCenter Resource WJessup, NRR BParks, NRR RidsOgcRp Resource SJones, NRR JPatel, NRR TWertz, NRR MKichline, NRR ASallman, NRR TSantos, EDO Region 3 GLapinsky, NRR TTate, NRR NMartinez, NRR ATsirigotis, NRR Package: ML12338A007 Meeting Notice: ML 12311A334 Meeting Summary: ML12338A006 EPU Gap Analysis Results Presentation Slides: ML12335A173 EPU Analysis -Details of Differences with NRCCorrespondence: ML 12335A176 OFFICE LPL3-1/PM LPL3-1/LAit LPL3-2/LA LPL3-1/BC LPL3-1/PM NAME TBeltz ELee SRohrer RCarlson TBeltz DATE 12/12/12 12/12/12 12/12/12 12/13/12 12/13/12 OFFICIAL RECORD COpy | | |
| }} | | List of Participants cc w/encl: Distribution via ListServ DISTRIBUTION |
| | : PUBLIC LPL3-1 R/F BBalsam, NRR MMcConnell, NRR RidsAcrsAcnw_MailCTR Resource CBasavaratu , NRR AMcMurtray, NRR RidsNrrDorlLpl3-1 Resource DDuvigneaud , NRR TMossman, NRR RidsNrrLASRohrer Resource Nlqbal, NRR MMurphy, NRR RidsNrrPMMonticelio Resource CJackson, NRR AObodoako, NRR RidsRgn3MailCenter Resource WJessup , NRR BParks, NRR RidsOgcRp Resource SJones, NRR JPatel, NRR TWertz, NRR MKichline, NRR ASallman, NRR TSantos , EDO Region 3 GLapinsky, NRR TTate, NRR NMartinez , NRR ATsirigotis , NRR Package: ML 12338A007 Meeting Notice: ML 12311A334 Meeting Summary: ML 12338A006 EPU Gap Analysis Results Presentation Slides: ML 12335A173 EPU Analysis -Details of Differences with NR CC orrespondence: |
| | ML 12335A176 OFFICE LPL3-1/PM LPL3-1/LAit LPL3-2/LA LPL3-1/BC LPL3-1/PM NAME TBeltz ELee SRohrer RCarlson TBeltz DATE 12/12/12 12/12/12 12/12/12 12/13/12 12/13/12 OFFICIAL RECORD COpy}} |
Letter Sequence Meeting |
---|
TAC:MD9990, Clarify Application of Setpoint Methodology for LSSS Functions (Approved, Closed) |
Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance, Acceptance
- Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement
Administration
- Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance
- Meeting, Meeting, Meeting, Meeting, Meeting, Meeting
Results
Other: L-MT-08-091, Calculation 0801040.301, Steam Dryer Outer Hood Submodel Analysis., L-MT-09-002, Response to NRC Probabilistic Risk Assessment (PRA) Branch Requests for Additional Information (Rais) Dated December 5, 2008, L-MT-09-003, Response to NRC Environmental Branch Requests for Additional Information (Rais) Dated December 18, 2008, L-MT-09-004, Enclosure 1 (Continued) to L-MT-09-004, NSPM Response to Containment & Ventilation Branch RAI Number 2, Copy of MNGP Appr T0406 Data Transmittal Pages 1 of 538 Through Pages 538 of 538, L-MT-09-026, Calculation 0000-0081-6958 MNGP-PRNMS-APRM Calc-2008-NP, Rev. 1, Average Power Range Monitor Selected Prnm Licensing Setpoints - EPU Operation (Numac), L-MT-09-027, Extended Power Uprate: Response to Instrumentation and Controls Branch RAI No. 3 Dated April 6, 2009, L-MT-09-044, Extended Power Uprate: Response to NRC Mechanical and Civil Engineering Review Branch (Emcb) Requests for Additional Information (Rais) Dated March 28, 2009, L-MT-09-049, Drawing C.5-2007, Revision 15, Failure to Scram, L-MT-09-073, Extended Power Uprate: Response to NRC Containment and Ventilation Review Branch (Scvb) Requests for Additional Information (Rais) Dated July 2, 2009 and July 14, 2009, L-MT-09-083, Extended Power Uprate: Limit Curves Requested by the Mechanical and Civil Review Branch (Emcb) Associated with Requests for Additional Information (Rais) Dated March 20, 2009, L-MT-09-088, Extended Power Uprate: Revision to Clarify Text in Enclosures 5 and 7 of L-MT-08-052, L-MT-09-097, Extended Power Uprate: Acknowledgement of NRC Review Delay, L-MT-10-025, Extended Power Uprate (Epu): Response to NRC-NSPM February 25, 2010 Conference Call, L-MT-10-072, Extended Power Uprate: Updates to Docketed Information, L-MT-11-044, Uprate (Epu): Update on EPU Commitments, L-MT-12-056, WCAP-17549-NP, Rev. 0, Monticello Replacement Steam Dryer Structural Evaluation for High-Cycle Acoustic Loads Using ACE, L-MT-12-090, Westinghouse, LTR-A&SA-12-8, Rev. 1, Attachment B, Recommendations for Inspections of the Monticello Replacement Steam Dryer., L-MT-12-114, Drawing C.5-2007, Rev. 17, Failure to Scram, L-MT-13-020, Enclosure 1 - Responses to the Gap Analysis, L-MT-13-029, Enclosure 14 to L-MT-13-029 - WCAP-17716-NP, Revision 0, Benchmarking of the Acoustic Circuit Enhanced Revision 2.0 for the Monticello Steam Dryer Replacement Project., L-MT-13-091, WCAP-17716-NP, Revision 1 - Benchmarking of the Acoustic Circuit Enhanced Revision 2.0 for the Monticello Steam Dryer Replacement Project, Enclosure 14, L-MT-13-092, Extended Power Uprate (Epu): Completion of EPU Commitments, Proposed License Conditions and Revised Power Ascension Test Plan, L-MT-13-096, GE-MNGP-AEP-3304R1, Enclosure 4, NEDC-33435 Corrected Pages, L-MT-13-126, Enclosure 3, GE-MNGP-AEP-3306, Enclosure 2 GEH Response to Mella+ Eicb RAI and Affidavit, L-MT-14-023, Maximum Extended Load Line Limit Analysis Plus: Technical Specification Clarifications, L-MT-15-074, Enclosure 7, WCAP-18604-NP, Revision 0, Monticello EPU Main Steam Line Strain Data Evaluation Report., L-MT-16-017, Revised Commitment to Reconcile Analysis of Bypass Voiding for Transition to Areva Analysis Methodology, L-MT-16-071, Submittal of 2016 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46, ML083230111, ML083400402, ML083500575, ML083570610, ML083590127, ML090710680, ML090710683, ML090710684, ML091120578, ML091140470, ML091410121, ML091410122, ML091410123, ML091410124, ML091760769, ML092290250, ML092810554, ML093160816, ML093220925, ML093220964, ML093620024, ML100280558... further results
|
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
[Table View] |
|
---|
Category:Meeting Summary
MONTHYEARML23313A1592023-11-0909 November 2023 U.S. Nuclear Regulatory Commission Summary of the October 10, 2023, Public Meeting to Discuss Monticello'S Condensate Backwash Receiving Tank Fatigue Evaluation ML23275A0222023-10-0505 October 2023 Summary of September 21, 2023, Public Meeting with Northern States Power Company Regarding Proposed License Amendment Request to Revise the Pressure Temperature Limits Report ML23200A2602023-07-20020 July 2023 Summary of July 14, 2023, Public Meeting with Northern States Power Company Regarding Proposed Alternative to Defer Periodic Verification Testing of Reactor Water Clean-Up Inboard Isolation Valve ML23157A0432023-06-0808 June 2023 Summary of Public Outreach to Discuss the NRC 2022 End-Of-Cycle Plant Performance Assessment of Monticello Nuclear Generating Plant ML23110A0142023-05-0101 May 2023 Memo March 22, 2023, Monticello Unit 1, Subsequent License Renewal Application Public Environmental Scoping Meeting ML23110A0152023-05-0101 May 2023 Summary March 22, 2023, Monticello Units 1 Subsequent License Renewal Application Public Environmental Scoping Meeting ML23115A4382023-05-0101 May 2023 March 29, 2023, Meeting Summary for Environmental Review of Subsequent License Renewal Application for Monticello Nuclear Generating Plant, Unit 1 ML23115A4642023-05-0101 May 2023 Summary, March 29, 2023, Monticello Units 1 Subsequent License Renewal Application Public Environmental Scoping Meeting ML23074A1212023-04-0303 April 2023 March 8, 2023, Summary of Public Meeting with Northern States Power Company Regarding Monticello Nuclear Generating Plant Alternative Request PR-08 to Defer Quarterly Testing of Components of High Pressure Coolant Injection System ML22292A0122022-10-24024 October 2022 Meeting Summary for Environmental Pre Submittal Meeting for Subsequent License Renewal Application, on September 13, 2022 ML22208A2192022-08-0303 August 2022 Summary of July 25, 2022, Meeting with Northern States Power Company, Doing Business as Xcel Energy, Related to the Amendment to Adopt Advanced Framatome Inc. Methodology for Determining Core Operating Limits for Monticello Plant ML22208A1952022-08-0303 August 2022 Summary of July 26, 2022, Meeting with Northern States Power Company, Doing Business as Xcel Energy, Related to the Alternative Request for Excess Flow Check Valves at Monticello Nuclear Generating Plant ML22130A7172022-05-10010 May 2022 Summary of the May 3, 2022, Public Outreach to Discuss the NRC 2021 End-Of-Cycle Plant Performance Assessment of Monticello and Prairie Island Nuclear Generating Plant, Units 1 and 2 ML22084A3852022-03-31031 March 2022 Meeting Summary for Environmental Pre Submittal Meeting for Subsequent License Renewal Application on March 15, 2022 ML22032A0112022-02-0303 February 2022 Summary of January 27, 2022, Meeting with Northern States Power Company, Doing Business as Xcel Energy, Related to a Planned Relief Request to Test Excess Flow Check Valve ML21285A0312021-10-15015 October 2021 Summary of Meeting with Northern States Power Company, Doing Business as Xcel Energy, Related to Planned License Amendment to Extend Allowed Outage Time for Fuel Oil Storage Tank for Monticello Nuclear Plant ML21167A1842021-06-16016 June 2021 Summary of the June 9, 2021, Public Outreach to Discuss the NRC 2020 End-Of-Cycle Plant Performance Assessment of Monticello Nuclear Generating Plant and Prairie Island Nuclear Generating Plant, Units 1 and 2 ML21098A0742021-04-13013 April 2021 Summary of March 25, 2021, Meeting with Northern States Power Company, Doing Business as Xcel Energy, Related to a Planned License Amendment to Adopt Advanced Framatome Methods ML21040A4612021-02-11011 February 2021 Summary of February 3, 2021, Meeting with Northern States Power Company, Doing Business as Xcel Energy, Related to a Planned License Amendment to Combine the Emergency Plans and Create a Common Emergency Operations Facility ML20281A5092020-10-16016 October 2020 Summary of October 2, 2020, Meeting with Northern States Power Company, Doing Business as Xcel Energy, on Potential Amendment to Revise the Safety Limit Minimum Critical Power Ratio for Monticello Nuclear Generating Plant ML20218A4462020-08-0505 August 2020 Summary of the July 16, 2020 Public Outreach to Discuss the NRC 2019 End-of-Cycle Plant Performance Assessment of Monticello Nuclear Generating Plant ML20077L8312020-03-20020 March 2020 Summary of February 27, 2020, Meeting with Northern States Power Company, Doing Business as Xcel Energy, on Potential License Amendment to Adopt TSTF-505 Provide Risk-Informed Completion Times - RITSTF Initiative 4b ML19130A1672019-05-14014 May 2019 May 8, 2019 Summary of Teleconference with Northern States Power Company, Doing Business as Xcel Energy, to Discuss a Response to a Request for Additional Information Related to the License Amendment Request to Adopt 10 CFR 50.69 ML18046B2072018-02-26026 February 2018 Summary of February 8, 2018, Meeting with Northern States Power Company, Doing Business as Xcel Energy, on Potential Exemption from Fire Protection Requirements at Monticello Nuclear Generating Plant Units 1 and 2 ML17353A0242018-01-0202 January 2018 Summary of December 12, 2017, Teleconference with Northern States Power Company, Doing Business as Xcel Energy, on Potential License Amendment Request to Adopt TSTF-425 ML17341A1292017-12-11011 December 2017 Summary of Meeting with Northern States Power Company, Doing Business as Xcel Energy, on Changes to the Security Plans at the Monticello Nuclear Generating Plant and Prairie Island Nuclear Generating Plant, Units 1 and 2 ML17300A0362017-10-31031 October 2017 Summary of Meeting with Northern States Power Company, Doing Business as Xcel Energy, on Potential License Amendment Request Related to Emergency Diesel Generator Technical Specifications ML17270A0072017-09-29029 September 2017 Summary of Teleconference with Northern States Power Company, Doing Business as Xcel Energy, on Potential License Amendment Request to Adopt TSTF-542 Reactor Pressure Vessel Water Inventory Control ML17235B1542017-08-23023 August 2017 July 11, 2017,Summary of the Open House to Discuss the 2016 End-Of-Cycle Plant Performance Assessment of Monticello ML17090A2442017-04-0606 April 2017 Summary of February 28, 2017, Meeting with Northern States Power Company, Doing Business as Xcel Energy, on the Integrated Leak Rate Test License Amendment Request for Monticello Nuclear Generating Plant CAC No. MF7359) ML17034A1202017-02-0909 February 2017 Summary of January 24, 2017, Meeting with Northern States Power Company, Doing Business as Xcel Energy, on Potential Revision to the Emergency Action Level ML16334A0112016-12-0606 December 2016 Summary of Meeting with Northern States Power Company, Doing Business as Xcel Energy, on Potential Exemption Request from Fire Protection Requirements ML16172A0662016-06-20020 June 2016 Summary of the May 26, 2016, Monticello Public Meeting ML15271A2072015-10-0202 October 2015 July 9, 2015 Summary of Closed Meeting Between Representatives of the U.S. Army Corps of Engineers, U.S, Nuclear Regulatory Commission and Northern States Power Company- Minnesota to Discuss Flood Analysis Associated with Monticello Nuclear ML15195A4472015-08-0505 August 2015 Summary of Public Meeting with Xcel Energy and Areva to Discuss Changes to the Proposed Technical Specifications and COLR in Support of the Areva Extended Flow Window License Amendment Request ML15093A2342015-04-0303 April 2015 Summary of Monticello Public Meeting ML14297A1272014-10-31031 October 2014 Summary of October 1, 2014, Public Meeting with NSPM and Areva to Discuss Areva Fuel Transition License Amendment Request and Future License Amendment Application Regarding Use of Areva Atrium 10XM Fuel in Extended Flow Window Domain ML14220A2832014-09-0808 September 2014 Summary of August 5, 2014, Closed Meeting Between Representatives of the U.S. Army Corps of Engineers, NRC, and Northern States Power Company - Minnesota to Discuss Flooding Analysis Associated with Monticello and Prairie Island Nuclear Gen ML14153A0252014-06-20020 June 2014 Meeting Summary - Public Meeting on May 16, 2014, to Discuss Xcel Energy'S Flood Hazard Reevaluation Extension Request for the Monticello and Prairie Island Nuclear Generating Plants ML14168A0182014-05-16016 May 2014 Xcel Energy Responses to NRC Questions Regarding Flood Hazard Reevaluation Report Extension Requests ML14111A0352014-04-21021 April 2014 Summary of Monticello Public Meeting to Discuss the 2013 Annual Assessment Results ML13351A3422013-12-30030 December 2013 December 4, 2013 Summary of Public Meeting with Northern States Power Company of Minnesota to Discuss the Future License Amendment Application Regarding the Use of Areva Atrium 10XM Fuel in Extended Flow Window Operating Domain ML13171A1522013-06-24024 June 2013 April 24, 2013, Summary of Public Meeting in City of Kewaunee to Make Post-Shutdown Decommissioning of Activities Report (PSDAR) Available for Public Comment ML13169A0352013-06-14014 June 2013 Email Miller to Wilson Summary of Call with Monticello Flooding Audit ML13135A0312013-05-31031 May 2013 Summary of May 3,2013, Conference Call with Northern States Power Company - Minnesota (NSPM) to Discuss Application of 10 CFR 26.205(d)(6) During the Current Refueling Outage ML12338A0062012-12-13013 December 2012 November 20, 2012, Summary of Public Meeting with Northern States Power Company of Minnesota to Discuss the Extended Power Uprate Gap Analysis ML12188A2582012-07-20020 July 2012 Summary of Meeting with Monticello Regarding a Future Amendment to Approve Use of Areva Atrium 10XM Fuel ML12093A4772012-05-0101 May 2012 April 2, 2012, Summary of Meeting with NSPM to Discuss Issue Related to Containment Accident Pressure Credit for Extended Power Uprate Operation ML12017A0852012-02-10010 February 2012 1/17/12 Summary of Meeting with Monticello a Future Application for Amendment Concerning Stored Fuel Criticality Analysis ML11292A1612011-10-20020 October 2011 Summary of Meeting with Beyond Nuclear Regarding Their 10 CFR 2.206 Petition to Suspend Operating Licenses of General Electric Mark I Boiling Water Reactors 2023-07-20
[Table view] |
Text
REG uZq UNITE D ST A
"'°11... NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001
<< 0 \n . : 0 V";. b Decem er 13, 2012 >t***i<
Northern States Power Company of Minnesota FACILITYMonticello Nuclear Generating Plant
SUMMARY
OF THE NOVEMBER 20, 2012 , PUBLIC MEETING WITH NORTHERN STATES POWER COMPANY OF MINNESOTA TO DISCUSS THE EXTENDED POWER UPRATE GAP ANALYSIS (TAC NO. MD9990) On November 20 , 2012, the U.S. Nuclear Regulatory Commission (NRC) staff held a Category 1 public meeting with representatives of Northern States Power Company of Minnesota, doing business as Xcel Energy, at NRC headquarters.
The purpose of the meeting was for the licensee to present the results of its extended power uprate (EPU) gap analysis. The gap analysis identifies changes to information previously submitted to the NRC in the EPU license amendment request (LAR) application and supplements.
The enclosure to this summary contains the list of participants.
The licensee introduced its EPU gap analysis in a slide presentation (docketed at Agencywide Documents Access and Management System (ADAMS) Accession No. ML 12335A173). The presentation summarized the history and current status of the Monticello EPU review , and provided the methodology for how the gap analysis results were identified and dispositioned. The focus of the meeting was a discussion of the gap analysis results, which Xcel Energy summarized in a table (docketed at ADAMS Accession No. ML 12335A176). The NRC staff questioned the licensee on various aspects of the table and provided the following comments listed below: Topic NRC Staff Comment(s) on Proposed Disposition
- Identify the ten MOVs Motor-Operated Valves
- Identify the impact on functional performance (MOVs)
- Discuss compliance with generic guidance
- Discuss remaining in compliance with 10 CFR 50 .55(a) Grid Stabil i ty
- Staff requests MISO [Midwest Independent Transmission Assessment System Operator]
letter be provided for review Environmental
- Staff requests a discussion of the changes and to provide Qualification (EQ) validation of EQ parameters Battery Capacity
-2 NRC Staff Comment(s) on Proposed Disposition Topic Staff understands that General Electric -Hitachi (GEH) is working on revising this calculation related to possible Main Steam Line High changes to choke flow rates Flow Trip Staff requests changes, when available, to be submitted for review Staff indicates a potential for follow-up discussions As long as changes are administrative in nature (i.e., results of calculations are unaffected), a brief description of Changes to Calculations the changes submitted on the docket should be sufficient If set point values are affected, then the staff requests the updated calculation be submitted for review Steam Dryer No specific comments Reactor Water Cleanup Staff requests that information related to change be Impact on Reactor Water submitted for review Quality EPU LAR for Pressure-Temperature Limits
- No specific comments LAR Staff requests verification that offsite dose still meets the limits of 40 CFR 190 with the addition of hydrogen water Noble Metals chemistry and noble metal injection Modification Licensee informed that there may be follow-up requests for additional information from NRC staff Abnormal Operating Staff requests information regarding the AOP change if the Procedure (AOP) turbine backpressure limit is changed Change Energy Core Cooling System (ECCS) Pump No specific comments Flow Rates Residual Heat Removal Core Spray Pump Room No specific comments Post-Loss-of-Coolant Accident Heatup Final Feedwater
- Staff commented on how GEH evaluated the effect of the Temperature change
-3 TODic NRC Staff Comment(s) on Proposed Disposition Piping Components Requiring Further Analysis
- Staff indicates that the change needs to be submitted and placed on the docket
- Describe the changes from the previous submittals
- Discuss if the changes are still bounding
- This will allow the staff to perform confirmatory calculations Condenser Free Volume
- Staff requests a table summarizing what changed and the assumptions being made Risk Assessment
- Staff indicates that the change needs to be submitted and placed on the docket
- No specific comments High-Energy Line Break
- No specific comments Appendix R
- Staff requests that the current licensing basis be clearly defined
- Clarification of the current requirement for 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> to :: 200°F
- Note: NRC fire protection staff requested validation of any changes impacting the fire protection analyses Containment Accident Pressure Review of Appendix R No specific comments *
-4 NRC Staff Comment(s) on Proposed Disposition Togic Reactor Head Spray Nozzle Fatigue
- No specific comments Assessment Emergency Operating Plan (EOP) Flow Chart Staff requests a copy of the EOP flowchart for ATWS for Anticipated Transfer Without Scram (A TWS) Avoidance of Trip of Both No specific comments, other than the staff will want to know Reactor Feed Pumps on if there is a commitment change Transients Staff indicates that information of what was reviewed to reach the conclusion that there are on impacts to the EA Environmental needs to be submitted and placed on the docket Assessment (EA) Staff recommends that the applicant refer to 10 CFR 50.92 when submitting changes list of Modifications
- No specific comments Required Provide a supplemental reload licensing report Provide an ECCS evaluation Staff requests a detailed discussion of changes to electrical equipment loading and capacities since the last submittal, Other NRC Staff including diesel generators Requests If Part 21 related to loss of stator cooling affects rvlNGP, provide an analytical assessment Staff requests review of RIS 2008-30 for applicability to MGNP Members of the public participated by telephone.
No portion of this meeting was closed to the public because no proprietary information or security-related information was discussed by the participants. Before the meeting adjourned, all participants were given the opportunity to comment on any aspects of the meeting. No comment or feedback was provided.
-Please direct any inquiries to me at 301-415-3049 or e-mail terry.beltz@nrc
.gov. Terry A. Beltz, Senior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket 1\10. 50-263
Enclosure:
List of Participants cc w/encl: Distribution via ListServ LIST OF MEETING BETWEEN THE U.S. NUCLEAR REGULATORY AND NORTHERN STATES POWER COMPANY OF MONTICELLO NUCLEAR GENERATING EXTENDED POWER UPRATE GAP ANALYSIS NOVEMBER NAME ORGANIZATION Briana Balsam f\I RC/NRR/DLR/RERB Chakrapani Basavaratu N RC/NRR/DE/EMCB Terry Beltz NRC/NRR/DORLlLPL3-1 William Bentley ** TVA Joel Beres IVlNGP John Bjorseth Xcel Energy Kevin Borton Exelon Robert Carlson N RC/N RR/DORLlLPL3-1 William Cheever ** MNGP Nicholas DiFrancesco N RC/N RR/DORLlLPL3-2 DyLanne Duvigneaud NRC/NRR/DRNAADB Gene Eckholt Xcel Energy Steve Frankl NRC/RES/DSNRSAB Peter Glass ** Xcel Energy Steve Hammer ** MNGP Nathan Haskell Xcel Energy Denzel Housley ** TVA Naeem Iqbal NRC/NRR/DRNAFPB Chris Jackson NRC/NRR/DSS/SRXB William Jessup N RC/NRRIDE/EMCB Steve Jones NRC/f\lRR/DSS/SBPB Aziz Khanifar Xcel Energy Michelle Kichline NRC/NRR/DRNAADB Jeff Kitsembel
- State of Wisconsin George Lapinsky ** NRC/NRRIDRNAHPB Nancy Martinez NRC/NRR/DLR/RERB Matthew McConnell NRC/NRR/DE/EEEB Tony McMurtray NRC/NRR/DE/EPTB Tim Mossman NRC/NRR/DE/EICB Marty Murphy I\JRC/NRR/DE/EMCB Ivy Netzel ** Performance Power Systems Aloysius Obodoako NRC/NRR/DE/ESGB John Osborne ** TV A (Browns Ferry) Ben Parks ** N RC/N RR/DSS/SRXB Jigar Patel NRC/NRR/DRNAPLA Enclosure LIST OF PARTICIPANTS (continued)
NAME Roger Pedersen Dave Pennington
- Participated by telephone ORGANIZATION NRC/NRRIDRAlAHPB MNGP N R CIt\! R RIDSS/SCVB I'J RC/NRRIDRAI MDB MNGP NRC/NRRIDE/EMCB Acronyms for List of Participants MDB AFPB AHPB APLA DE DLR DORL DRA DSS EEEB EICB EMCB ESGB EPTB LPL3-1 LPL3-2 rvlNGP NRC NRR RERB RES SBPB SCVB SRXB TVA Accident Dose Branch Fire Protection Branch Health Physics & Human Performance Branch PRA Licensing Branch Division of Engineering Division of License Renewal Division of Operating Reactor Licensing Division of Risk Assessment Division of Safety Systems Electrical Engineering Branch Instrumentation and Controls Branch Mechanical
& Civil Engineering Branch Steam Generator Tube Integrity
& Chemical Engineering Branch Component Performance
& Testing Branch Plant Licensing Branch 111-1 Plant Licensing Branch 111-2 Monticello Nuclear Generating Plant U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Environmental Review & Guidance Update Branch Office of Nuclear Research Balance-of-Plant Branch Containment and Ventilation Branch Reactor Systems Branch Tennessee Valley Authority
-5 Please direct any inquiries to me at 301-415-3049 or e-mail terry.beltz@nrc.gov. Terry A. Beltz , Senior Project Manager IRAJ Plant Licensing Branch" 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-263
Enclosure:
List of Participants cc w/encl: Distribution via ListServ DISTRIBUTION
- PUBLIC LPL3-1 R/F BBalsam, NRR MMcConnell, NRR RidsAcrsAcnw_MailCTR Resource CBasavaratu , NRR AMcMurtray, NRR RidsNrrDorlLpl3-1 Resource DDuvigneaud , NRR TMossman, NRR RidsNrrLASRohrer Resource Nlqbal, NRR MMurphy, NRR RidsNrrPMMonticelio Resource CJackson, NRR AObodoako, NRR RidsRgn3MailCenter Resource WJessup , NRR BParks, NRR RidsOgcRp Resource SJones, NRR JPatel, NRR TWertz, NRR MKichline, NRR ASallman, NRR TSantos , EDO Region 3 GLapinsky, NRR TTate, NRR NMartinez , NRR ATsirigotis , NRR Package: ML 12338A007 Meeting Notice: ML 12311A334 Meeting Summary: ML 12338A006 EPU Gap Analysis Results Presentation Slides: ML 12335A173 EPU Analysis -Details of Differences with NR CC orrespondence:
ML 12335A176 OFFICE LPL3-1/PM LPL3-1/LAit LPL3-2/LA LPL3-1/BC LPL3-1/PM NAME TBeltz ELee SRohrer RCarlson TBeltz DATE 12/12/12 12/12/12 12/12/12 12/13/12 12/13/12 OFFICIAL RECORD COpy