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MONTHYEARL-MT-14-022, the Comprehensive Methodology for Challenging BWR Fuel Assembly and Core Design Used at Framatome Anp2002-10-10010 October 2002 the Comprehensive Methodology for Challenging BWR Fuel Assembly and Core Design Used at Framatome Anp Project stage: Other ML13247A4522013-09-0404 September 2013 NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance Review License Amendment Request to Transition to Areva Atrium 10XM Fuel & Areva Safety Analysis Methodology Project stage: Acceptance Review ML13353A3662013-12-18018 December 2013 NRR E-mail Capture - Monticello Nuclear Generating Plant - Request for Additional Information NRC Staff Review of Areva Fuel Transition License Amendment Request Project stage: Approval L-MT-14-003, Enclosures 2 & 3 to L-MT-14-003, ANP-3286NP, Rev. 0, Responses to RAI from Srxb on MNGP Transition to Areva Fuel & Areva Atrium 10XM Fuel Transition - Response to Requests for Additional Information2014-01-31031 January 2014 Enclosures 2 & 3 to L-MT-14-003, ANP-3286NP, Rev. 0, Responses to RAI from Srxb on MNGP Transition to Areva Fuel & Areva Atrium 10XM Fuel Transition - Response to Requests for Additional Information Project stage: Response to RAI ML14035A2982014-01-31031 January 2014 Areva Atrium 10XM Fuel Transition - Response to Request for Additional Information Project stage: Response to RAI ML14077A3022014-03-12012 March 2014 Areva Atrium 10XM Fuel Transition - Response to Request for Additional Information Project stage: Request ML14090A0052014-03-27027 March 2014 NRR E-mail Capture - Monticello Nuclear Generating Plant - NRC Staff Request for Additional Information (Follow-up Question) Areva Fuel Transition License Amendment Request Project stage: RAI L-MT-14-033, Areva Atrium 10XM Fuel Transition - Supplement to Describe the Effect of Local Power Range Monitor Surveillance Grace Period2014-04-29029 April 2014 Areva Atrium 10XM Fuel Transition - Supplement to Describe the Effect of Local Power Range Monitor Surveillance Grace Period Project stage: Supplement L-MT-14-041, ANP-3304NP, Rev. 0, Areva Response to NRC Follow-Up on Srxb RAI-6: ASME Overpressure Analysis.2014-05-0909 May 2014 ANP-3304NP, Rev. 0, Areva Response to NRC Follow-Up on Srxb RAI-6: ASME Overpressure Analysis. Project stage: Other ML14132A1942014-05-0909 May 2014 Areva Atrium 10XM Fuel Transition - Response to Request for Additional Information Project stage: Response to RAI L-MT-14-042, Areva Atrium 10XM Fuel Transition - Errata Re License Amendment Request2014-05-0909 May 2014 Areva Atrium 10XM Fuel Transition - Errata Re License Amendment Request Project stage: Request ML14155A1672014-07-0808 July 2014 Request for Withholding Information from Public Disclosure Associated with Affidavit Executed on January 23, 2014, by Mr. Alan B. Meginnis of Areva Np, Inc. Project stage: Withholding Request Acceptance ML14155A1692014-07-0808 July 2014 Request for Withholding Information from Public Disclosure Associated with Affidavit Executed on April 22, 2014, by Mr. Alan B. Meginnis of Areva Inc. Project stage: Withholding Request Acceptance ML14155A1772014-07-0808 July 2014 Request for Withholding Information from Public Disclosure Associated with Affidavit Executed on April 28, 2014, by Mr. Philip A. Opsal of Areva Inc. Project stage: Withholding Request Acceptance ML15154A4772015-06-0505 June 2015 Safety Evaluation Regarding License Amendment No. 188 Associated with Areva Atrium 10XM Fuel Transition (TAC No. MF2479) - (Redacted) Project stage: Approval ML15072A1412015-06-0505 June 2015 Issuance of Amendment No. 188 Regarding Transition to Areva Atrium 10XM Fuel and Areva Safety Analysis Methods Project stage: Approval L-MT-15-091, Submittal of 2015 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.462015-12-22022 December 2015 Submittal of 2015 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46 Project stage: Request L-MT-16-027, Annual Report of Changes in Areva Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.462016-05-24024 May 2016 Annual Report of Changes in Areva Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46 Project stage: Other 2014-03-27
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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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ENCLOSURES 1 AND 3 CONTAIN PROPRIETARY INFORMATION WITHHOLD FROM PUBLIC DISCLOSURE IN ACCORDANCE WITH 10 CFR 2.390@ XcelEnergy" March 12, 2014 Monticello Nuclear Generating Plant 2807 W County Rd 75 Monticello, MN 55362 L-MT-14-022 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:
AREVA ATRIUM 1OXM Fuel Transition
-Response to Request for Additional Information (TAC MF2479)
References:
1)Letter from M. A. Schimmel (NSPM), to Document Control Desk (NRC), "License Amendment Request for Transition to AREVA ATRIUM 1OXM Fuel and AREVA Safety Analysis Methodology," L-MT-13-055, dated July 15, 2013. (ADAMS Accession No.ML13200A185)
- 2) Email from T. Beltz (NRC) to G. Adams (NSPM), "Monticello Nuclear Generating Plant -Request for Additional Information re: Review of AREVA Fuel Transition License Amendment Request (TAC MF2479)," dated January 30, 2014.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 using AREVA ATRIUM 1OXM fuel.In Reference 2 the NRC provided Requests for Additional Information (RAIs) pertaining to information needed to support the Fuel Transition License Amendment Request (Reference 1). The purpose of this letter is to provide NSPM's responses to the Reference 2 RAIs.
Document Control Desk Page 2 Enclosure 1 provides AREVA Report, ANP-3289P, Revision 0, "Responses to RAI from SNPB on MNGP Transition to AREVA Fuel." This enclosure provides a response to NRC RAIs from Reference
- 2. Enclosure 1 contains proprietary information.
Enclosure 2 provides a non-proprietary copy of the Enclosure 1 RAI responses.
The non-proprietary copy of the RAI responses 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 3 provides EMF-CC-167(P), Revision 8, XCOBRA-T Theory, Programmer's, and User's Manual, November 2011. This document is being provided based on the NRC's request in RAI-18. This document is proprietary in its entirety and thus no non-proprietary version has been provided.Enclosure 4 provides "The Comprehensive Methodology for Challenging BWR Fuel Assembly and Core Design used at Framatome ANP," S. Misu et al., PHYSOR 2002, Seoul, Korea, October 7-10, 2002. This document is being provided based on the NRC's request in RAI-21.Enclosure 5 provides affidavits executed to support withholding Enclosures 1 and 3 from public disclosure.
Information in Enclosures 1 and 3 contain proprietary information as defined by 10 CFR 2.390. The affidavits set 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 AREVA proprietary information in Enclosures 1 and 3 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 the AREVA information in Enclosures 1 and 3 or the supporting AREVA affidavits in Enclosure 5 should be addressed to Mr. Alan Meginnis, Manager, Product Licensing, AREVA Inc., 2101 Horn Rapids Road, Richland, Washington 99354.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 AREVA Fuel Transition 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 or revisions to existing commitments.
Document Control Desk Page 3 I declare under penalty of perjury that the foregoing is true and correct.Executed on: March/2, 2014 Karen D. Fili Site Vice-President Monticello Nuclear Generating Plant Northern States Power Company-Minnesota Enclosures (5)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)