Letter Sequence Approval |
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MONTHYEARL-MT-13-038, Mngp'S Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2013-04-29029 April 2013
Mngp'S Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident
Project stage: Response to RAI
L-MT-13-088, Request Commitment Change for Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.1 of the Nearterm Task Force Review of Insights from the Fukushima Dai-ichi Accident2013-09-12012 September 2013
Request Commitment Change for Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.1 of the Nearterm Task Force Review of Insights from the Fukushima Dai-ichi Accident
Project stage: Response to RAI
L-MT-14-027, Request Commitment Change for Response to NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(D Regarding the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights From2014-03-31031 March 2014
Request Commitment Change for Response to NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(D Regarding the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights From.
Project stage: Request
ML14136A2892014-05-12012 May 2014
14C4229-RPT-001, Revision 3, Monticello Nuclear Generating Plant Seismic Hazard and Screening Report.
Project stage: Request
L-MT-14-093, Expedited Seismic Evaluation Process (ESEP) - Augmented Approach to Post-Fukushima Near-Term Task Force (NTTF) 2.12014-12-23023 December 2014
Expedited Seismic Evaluation Process (ESEP) - Augmented Approach to Post-Fukushima Near-Term Task Force (NTTF) 2.1
Project stage: Request
L-MT-15-030, Expedited Seismic Evaluation Process (ESEP) - Augmented Approach to Post-Fukushima Near-Term Task Force (NTTF) 2.1 - Response to Requests for Additional Information2015-05-22022 May 2015
Expedited Seismic Evaluation Process (ESEP) - Augmented Approach to Post-Fukushima Near-Term Task Force (NTTF) 2.1 - Response to Requests for Additional Information
Project stage: Response to RAI
L-MT-15-060, Expedited Seismic Evaluation Process (ESEP) - Augmented Approach to Post-Fukushima Near-Term Task Force (NTTF) 2.1 - Clarification of Response to Request for Additional Information2015-08-13013 August 2015
Expedited Seismic Evaluation Process (ESEP) - Augmented Approach to Post-Fukushima Near-Term Task Force (NTTF) 2.1 - Clarification of Response to Request for Additional Information
Project stage: Response to RAI
ML15272A4212015-09-0404 September 2015
NRR E-mail Capture - Monticello Nuclear Station, Unit 1 - Technical Review Checklist Related to Interim ESEP Supporting Implementation of NTTF R2.1, Seismic
Project stage: Other
ML15281A0292015-10-14014 October 2015
Staff Review of Interim Evaluation Associated with Reevaluated Seismic Hazard Implementing Near-Term Task Force Recommendation 2.1
Project stage: Approval
2014-05-12
[Table View] |
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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
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 October 14, 2015 Mr. Peter A. Gardner Site Vice President Northern States Power Company - Minnesota Monticello Nuclear Generating Plant 2807 West County Road 75 Monticello, MN 55362-9637
SUBJECT:
MONTICELLO NUCLEAR GENERATING PLANT-STAFF REVIEW OF INTERIM EVALUATION ASSOCIATED WITH REEVALUATED SEISMIC HAZARD IMPLEMENTING NEAR-TERM TASK FORCE RECOMMENDATION 2.1 (TAC NO. MF5251)
Dear Mr. Gardner:
By letter dated March 12, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12053A340), the U.S. Nuclear Regulatory Commission (NRC) issued a request for information pursuant to Title 1O of the Code of Federal Regulations Part 50, Section 50.54(f) (hereafter referred to as the 50.54(f) letter). The request was issued as part of implementing lessons-learned from the accident at the Fukushima Dai-ichi nuclear power plant. to the 50.54(f) letter requested that licensees reevaluate seismic hazards at their sites using present-day methodologies and guidance. Enclosure 1, Item 6, of the 50.54(f) letter requested that licensees identify "interim evaluation and actions taken or planned to address the higher seismic hazard relative to the design basis as appropriate, prior to completion of the (seismic] risk evaluation." In addition to the interim evaluation provided in the March 2014 Seismic Screening and Hazard report, the licensees for the Central and Eastern United States committed to providing the Expedited Seismic Evaluation Process (ESEP) report, an interim evaluation, by December 31, 2014.
By letter dated December 23, 2014 1 , Northern States Power Company - Minnesota (NSPM, the licensee) doing business as Xcel Energy, provided its ESEP report in a response to Enclosure 1, Item (6) of the 50.54(f) letter, for the Monticello Nuclear Generating Plant (Monticello). The NRC staff assessed the licensee's implementation of the ESEP guidance through the completion of a reviewer checklist 2 . In support of NRC staff questions, Xcel Energy provided responses dated May 22, 2015, and August 13, 2015 3 , clarifying submittal information. Based on the NRC staff review of the ESEP report and responses to the staff's questions, the NRC staff concludes that the licensee's implementation of the interim evaluation meets the intent of the guidance.
1 The December 23, 2014, letter can be found under ADAMS Accession No. ML14357A280.
2 The Monticello ESEP NRC review checklist can be found under ADAMS Accession No. ML15272A421 3 The Xcel Energy responses to NRC staff questions can be found ADAMS Accession Nos.
ML15142A862 and ML15225A463.
P. Gardner The staff concludes that, through the implementation of the ESEP guidance, the licensee identified and evaluated the seismic capacity of certain key installed Mitigating Strategies equipment that is used for core cooling and containment functions to cope with scenarios that involve a loss of all alternating current power and loss of access to the ultimate heat sink to withstand a seismic event 1.49 times the safe shutdown earthquake for Monticello. The licensee has demonstrated additional assurance which supports continued plant safety while the longer-term seismic evaluation is completed to support regulatory decision making. The NRC staff concludes that the licensee responded appropriately to Enclosure 1, Item (6) of the 50.54(f) letter. Application of this review is limited to the interim evaluation as part of R2.1 Seismic review The NRC staff notes that a summary of regulatory commitments to complete ESEP activites is documented in the response to request for additional information No. 7 in the May 22, 2015, letter. A letter will be provided to the NRC indicating the proposed resolution applicable to each component in Section 8.2 of the Monticello ESEP Report and the expected timeframe for completion of the resolution when this information has been developed. A letter will be provided to the NRC summarizing the High Confidence of Low Probability of Failure results of each component and confirming the resolution of each component. This letter will be sent within 60-days of completion of the resolution activities for the final completed component from Table 7-1 of the May 22, 2015, letter.
If you have any questions, please contact me at (301) 415-1115 or via e-mail at Nicholas DiFrancesco@nrc.gov.
Sincerely, Nicholas DiFrancesco, Senior Project Manager Hazards Management Branch Japan Lessons-Learned Division Office of Nuclear Reactor Regulation Docket No. 50-263 cc: Distribution via Listserv
P. Gardner The staff concludes that, through the implementation of the ESEP guidance, the licensee identified and evaluated the seismic capacity of certain key installed Mitigating Strategies equipment that is used for core cooling and containment functions to cope with scenarios that involve a loss of all alternating current power and loss of access to the ultimate heat sink to withstand a seismic event 1.49 times the safe shutdown earthquake for Monticello. The licensee has demonstrated additional assurance which supports continued plant safety while the longer-term seismic evaluation is completed to support regulatory decision making. The NRC staff concludes that the licensee responded appropriately to Enclosure 1, Item (6) of the 50.54(f) letter. Application of this review is limited to the interim evaluation as part of R2.1 Seismic review The NRC staff notes that a summary of regulatory commitments to complete ESEP activites is documented in the response to request for additional information No. 7 in the May 22, 2015, letter. A letter will be provided to the NRC indicating the proposed resolution applicable to each component in Section 8.2 of the Monticello ESEP Report and the expected timeframe for completion of the resolution when this information has been developed. A letter will be provided to the NRC summarizing the High Confidence of Low Probability of Failure results of each component and confirming the resolution of each component. This letter will be sent within 60-days of completion of the resolution activities for the final completed component from Table 7-1 of the May 22, 2015, letter.
If you have any questions, please contact me at (301) 415-1115 or via e-mail at Nicholas DiFrancesco@nrc.gov.
Sincerely, IRA/
Nicholas DiFrancesco, Senior Project Manager Hazards Management Branch Japan Lessons-Learned Division Office of Nuclear Reactor Regulation Docket No. 50-263 cc: Distribution via Listserv DISTRIBUTION:
PUBLIC RidsNrrPMMonticello RidsN rrLASLent RidsNrrOd LPL3-1 R/F RidsNrrDorllpl3-1 RidsRgn3MailCenter DJackson, NRO JLD R/F NDiFrancesco, NRR MShams, NRR ADAMS Accession Number: ML15281A029 *via e-mail OFFICE NRR/JLD/JHMB/PM NRR/JLD/LA DSENRGS2/BC NAME SWyman Slent DJackson*
DATE 10/8/2015 10/9/2015 9/4/2015 OFFICE NRR/JLD/JHMB/BC NRR/JLD/JHMB/PM NAME MS hams NDiFrancesco DATE 10/14/2015 10/14/2015 OFFICIAL RECORD COPY
