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MONTHYEARML16133A0412016-05-0909 May 2016 Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 2, Flood Hazard Reevaluation Report Project stage: Request ML16152A1262016-06-0707 June 2016 Nuclear Regulatory Commission Plan for the Audit of Northern States Power Company Minnesota'S Flood Hazard Reevaluation Report Submittal Relating to the Near-Term Task Force Recommendation 2.1-Flooding Prairie Island Nuclear Generating Plan Project stage: Other ML16189A4022016-07-0707 July 2016 Xcel Energy - 6/29/16 Webinar Summary for Prairie Island Nuclear Generating Plant Flood Hazard Reevaluation Report Interim Actions Project stage: Other ML16248A0062016-09-16016 September 2016 Interim Staff Response to Reevaluated Flood Hazards Submitted in Response to 10 CFR 50.54(f) Information Request - Flood-Causing Mechanism Reevaluation (CAC Nos. MF7710 and MF7711) Project stage: Other ML16245A7632016-09-16016 September 2016 MSFHI Tables Final 8-31-2016 Project stage: Other ML16279A4792016-09-29029 September 2016 Flood Hazard Reevaluation Report - Response to Requested Information Project stage: Other ML16280A0352016-09-29029 September 2016 Flood Hazard Reevaluation Report - Response to Requested Information (CAC Nos. MF7710 and MF7711) - Figure 1 of 3 Project stage: Other ML16280A0372016-09-29029 September 2016 Flood Hazard Reevaluation Report - Response to Requested Information (CAC Nos. MF7710 and MF7711) - Figure 2 of 3 Project stage: Other ML16280A0422016-09-29029 September 2016 Flood Hazard Reevaluation Report - Response to Requested Information (CAC Nos. MF7710 and MF7711) - Figure 3 of 3 Project stage: Other ML17097A1962017-04-18018 April 2017 Audit Report Relating to the Flood Hazard Reevaluation Report Project stage: Other ML17144A1542017-05-26026 May 2017 Staff Assessment of Response to 10 CFR 50.54(F) Information Request - Flood-Causing Mechanism Reevaluation (CAC Nos. MF7710 and MF7711 - Redacted Version Project stage: Other 2016-09-16
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Category:Audit Plan
MONTHYEARML16259A1892016-12-0505 December 2016 Nuclear Regulatory Commission Plan for the Audit of Mitigation Strategies Assessment Submittals Related to Order EA-12-049, Order to Modify Licenses With Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events ML16152A1262016-06-0707 June 2016 Nuclear Regulatory Commission Plan for the Audit of Northern States Power Company Minnesota'S Flood Hazard Reevaluation Report Submittal Relating to the Near-Term Task Force Recommendation 2.1-Flooding Prairie Island Nuclear Generating Plan ML15083A4152015-03-31031 March 2015 Plan for the Onsite Audit Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 ML15054A0022015-02-25025 February 2015 Regulatory Audit in Support of NFPA 805 License Amendment Request ML14083A6202014-03-26026 March 2014 Nuclear Regulatory Commission Audits of Licensee Responses to Reliable Spent Fuel Pool Instrumentation Order EA-12-051 2016-06-07
[Table view] Category:Letter
MONTHYEARIR 05000282/20230042024-02-0101 February 2024 Integrated Inspection Report 05000282/2023004 and 05000306/2023004 ML23356A1232024-01-29029 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting) 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 ML24017A0182024-01-19019 January 2024 Confirmation of Initial License Examination ML23356A0032024-01-17017 January 2024 Issuance of Amendments Revise Technical Specification 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) L-PI-23-034, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.7.8, Cooling Water (Cl) System,2024-01-0202 January 2024 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.7.8, Cooling Water (Cl) System, L-PI-23-035, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report2023-12-20020 December 2023 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report IR 07200010/20234012023-12-20020 December 2023 Independent Spent Fuel Storage Installation Security Inspection Report 07200010/2023401 ML23349A0572023-12-15015 December 2023 and Independent Spent Fuel Storage Installation, Revision to Correspondence Service List for Northern States Power - Minnesota ML23215A1672023-12-15015 December 2023 Acceptance of Requested Licensing Action Amendment Request to Revise Surveillance Requirement 3.8.1.2 Note 3 IR 05000282/20234012023-12-13013 December 2023 Security Baseline Inspection Report 05000282/2023401 and 05000306/2023401 L-PI-23-033, Supplement to License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 32023-12-0505 December 2023 Supplement to License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 3 ML23304A1632023-11-15015 November 2023 Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment Request to Revise SR 3.8.1.2 Note 3 ML23319A3182023-11-15015 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000282/20230032023-11-0808 November 2023 Integrated Inspection Report 05000282/2023003 and 05000306/2023003 ML23311A3572023-11-0707 November 2023 Core Operating Limits Report (COLR) for Prairie Island Nuclear Generating Plant (PINGP) Unit 2. Cycle 33. Revision 0 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 ML23270B9022023-09-29029 September 2023 Review of Reactor Vessel Material Surveillance Program Capsule N Technical Report L-PI-23-025, License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 32023-09-28028 September 2023 License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 3 ML23265A2532023-09-26026 September 2023 Review of Reactor Vessel Material Surveillance Program Capsule N Technical Report ML23262B0372023-09-19019 September 2023 Response to NRC Request for Additional Information Regarding the 2023 Monticello and Prairie Island Plant Decommissioning Funding Status Reports 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 L-PI-23-023, Baffle Former Bolts Alternate Aging Management Strategy2023-09-11011 September 2023 Baffle Former Bolts Alternate Aging Management Strategy IR 05000282/20230052023-08-30030 August 2023 Updated Inspected Plan for Prairie Island Nuclear Generating Plant Report 05000282/2023005 and 05000306/2023005 IR 05000282/20230102023-08-17017 August 2023 NRC Inspection Report 05000282/2023010 and 05000306/2023010 ML23222A0122023-08-10010 August 2023 Independent Spent Fuel Storage Installation and Monticello Nuclear Generating Plant - Changes in Foreign Ownership, Control or Influence IR 05000282/20230022023-08-0303 August 2023 Integrated Inspection Report 05000282/2023002 and 05000306/2023002 ML23214A2032023-08-0202 August 2023 Request for Information for an NRC Quadrennial Comprehensive Engineering Team Inspection: Inspection Report 05000282/2024010; 05000306/2024010 ML23206A2342023-07-25025 July 2023 Independent Spent Fuel Storage Installation, and Monticello Nuclear Generating Plant, Changes in Foreign Ownership, Control or Influence 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) ML23199A0922023-07-18018 July 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000306/2023004 ML23195A1732023-07-14014 July 2023 Revision of Standard Practice Procedures Plan L-PI-23-018, License Amendment Request to Revise ISFSI Technical Specification 4.4 to Allow Use of a Code Alternative to ASME Code, NB-5130, Examination of Weld Edge Preparation Surfaces, for the TN-40HT2023-07-14014 July 2023 License Amendment Request to Revise ISFSI Technical Specification 4.4 to Allow Use of a Code Alternative to ASME Code, NB-5130, Examination of Weld Edge Preparation Surfaces, for the TN-40HT ML23181A0192023-06-30030 June 2023 Independent Spent Fuel Storage Installation, Revision to Correspondence Service List for Northern States Power - Minnesota ML23178A2422023-06-28028 June 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III L-PI-23-006, License Amendment Request to Revise Technical Specification 3.7.8 Required Actions2023-06-22022 June 2023 License Amendment Request to Revise Technical Specification 3.7.8 Required Actions L-PI-23-016, 2022 10 CFR 50.46 LOCA Annual Report2023-06-14014 June 2023 2022 10 CFR 50.46 LOCA Annual Report IR 05000282/20234202023-06-0101 June 2023 Security Baseline Inspection Report 05000282/2023420 and 05000306/2023420 ML23150A1722023-05-30030 May 2023 Preparation and Scheduling of Operator Licensing Examinations 2024-02-01
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 June 7, 2016 Mr. Scott D. Northard Acting Site Vice President Northern States Power Company - Minnesota Prairie Island Nuclear Generating Plant 1717 Wakonade Drive East Welch, MN 55089-9642
SUBJECT:
NUCLEAR REGULATORY COMMISSION PLAN FOR THE AUDIT OF NORTHERN STATES POWER COMPANY - MINNESOTA'S FLOOD HAZARD REEVALUATION REPORT SUBMITTAL RELATING TO THE NEAR-TERM TASK FORCE RECOMMENDATION 2.1-FLOODING PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1AND2 (CAC NOS. MF7710, MF7711)
Dear Mr. Northard:
This letter documents the U.S. Nuclear Regulatory Commission (NRC) staff's plan to perform a regulatory audit of Northern States Power Company's (the licensee), doing business as Xcel Energy, supporting calculations for the Flood Hazard Reevaluation Report (FHRR) submittal related to the Near-Term Task Force Recommendation 2.1, Flooding for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Prairie Island). This technical audit will be performed consistent with NRC Office of Nuclear Reactor Regulation , Office Instruction LIC-111 , and "Regulatory Audits ," dated December 29, 2008 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML082900195). The audit will be conducted over multiple sessions, as needed , and the NRC staff will develop an audit summary report to document its observations and conclusions within 90 days of the final audit session.
The audit will provide the NRC staff with a better understanding of the Prairie Island FHRR, which was submitted by letter dated May 9, 2016 (ADAMS Accession No. ML16133A041).
Specifically, the audit will provide the NRC with a better understanding of the analyses of the flooding hazards presented in the Prairie Island FHRR. The audit is intended to support completion of the staff's review of the FHRR and the subsequent issuance of a staff assessment.
The enclosed audit plan outlines the process that will allow the NRC staff to identify additional information potentially necessary for licensees to supplement their FHRRs and resolve potential technical concerns . The NRC staff discussed the details of this audit with Mrs. Lynne Gunderson and Mr. Gene Eckholt of your staff.
S. Northard If you have any questions, please contact me at (301) 415-6185 or by e-mail at Victor.Hall@nrc.gov.
Victor Hall , Senior Project Manager Hazards Management Branch Japan Lessons-Learned Division Office of Nuclear Reactor Regulation Docket Nos. 50-282 and 50-306
Enclosure:
Audit Plan cc w/encl : Distribution via Listserv
NRC PLAN FOR THE AUDIT OF NORTHERN STATES POWER COMPANY - MINNESOTA'S FLOODING HAZARD REEVALUATION REPORT SUBMITTAL RELATING TO THE NEAR-TERM TASK FORCE RECOMMENDATION 2.1-FLOODING FOR PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1AND2 BACKGROUND AND AUDIT BASIS:
By letter dated March 12, 2012, the U.S . Nuclear Regulatory Commission (NRC) issued a request for information to all power reactor licensees and holders of construction permits in active or deferred status, pursuant to Title 10 of the Code of Federal Regulations (1 O CFR) ,
Section 50.54(f) "Conditions of license" (hereafter referred to as the "50.54(f) letter"). The request was issued in connection with implementing lessons-learned from the 2011 accident at the Fukushima Dai-ichi nuclear power plant, as documented in the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident. Recommendation 2.1 of that document recommended that the staff issue orders to all licensees to reevaluate seismic and flooding for their sites against current NRC requirements and guidance. Subsequent Staff Requirements Memoranda associated with Commission Papers SECY 11 -0124 and SECY-11-0137, instructed the NRC staff to issue requests for information to licensees pursuant to 10 CFR 50.54(f) .
By letter dated May 9, 2016, Northern States Power Company - Minnesota (NSPM , the licensee), doing business as Xcel Energy, submitted its Flood Hazard Reevaluation Report (FHRR) for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Prairie Island) (Agencywide Documents Access and Management System Accession No. ML16133A041 ). The NRC staff has begun its review of the aforementioned submittals and plans to conduct a regulatory audit of NSPM to aid in its review of the licensee's FHRR.
REGULA TORY AUDIT SCOPE AND METHODOLOGY:
The areas of focus for the regulatory audit is the information contained in the Prairie Island FHRR submittal, and all associated and relevant supporting documentation used in the development of the aforementioned document including , but not limited to, methodology, process information , calculations , computer models, etc. The audit will be conducted and completed over a small number of meetings that are to be determined , as necessary.
Enclosure
INFORMATION AND OTHER MATERIAL NECESSARY FOR THE REGULATORY AUDIT:
The information required for the audit is the licensee's models and supporting calculations , as well as documentation related to the storm surge and site specific probable maximum precipitation analyses. Other information needs will be discussed as audit meetings are scheduled .
NRC AUDIT TEAM:
Title Team Member Affiliation Team Leader, NRR/JLD Victor Hall NRC Branch Chief, NRO/DSEA Aida Rivera-Varona NRC Technical Lead Peter Chaput NRC Technical Support To Be Determined Oak Ridge National Laboratory Technical Support To Be Determined Taylor Engineering LOGISTICS:
The audit meetings will be coordinated with NSPM staff.
DELIVERABLES:
The NRC team will develop an audit summary report to convey the audit results . The report will be placed in ADAMS within 90 days of the completion of the final audit session, and will be publicly available.
The information discussed in the audit may be included , fully or in part, in the development of the NRC technical staff's assessments as a result of the FHRR review.
ML16152A126 OFFICE NRR/JLD/JHMB/PM NRR/JLD/JHMB/LA NRR/JLD/JHMB/BC NRR/JLD/JHMB/PM NAME VHall Slent MShams VHall DATE 05/27/2016 05/31/2016 06/07/2016 06/07/2016