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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
MONTHYEARML24277A1012024-10-0303 October 2024 Closure of Interim Report of a Potential Deviation or Failure to Comply Associated with Bentley Systems Incorporated Autopipe Software ML24241A1682024-09-23023 September 2024 Transmittal Letter Amendment No. 13 to Materials License No. Special Nuclear Material-2506 for the Prairie Island Independent Spent Fuel Storage Installation 05000282/LER-2024-001, Auxiliary Building Special Ventilation System Inoperable During Movement of Irradiated Fuel Assemblies2024-09-16016 September 2024 Auxiliary Building Special Ventilation System Inoperable During Movement of Irradiated Fuel Assemblies IR 05000282/20243012024-09-13013 September 2024 NRC Initial License Examination Report 05000282/2024301 and 05000306/2024301 IR 05000282/20240052024-08-28028 August 2024 Updated Inspection Plan and Assessment Follow-Up Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report 05000282/2024005 and 05000306/2024005) L-PI-24-040, Post-Submittal Package Letter2024-08-23023 August 2024 Post-Submittal Package Letter IR 05000282/20245012024-08-0505 August 2024 Emergency Preparedness Inspection Report 05000282/2024501 and 05000306/2024501 ML24213A1592024-07-31031 July 2024 Operator Licensing Examination Approval - Prairie Island Nuclear Generating Plant IR 05000282/20240022024-07-30030 July 2024 Integrated Inspection Report 05000282/2024002 and 05000306/2024002 ML24208A1502024-07-26026 July 2024 Independent Spent Fuel Storage Installation - Submittal of Quality Assurance Topical Report (NSPM-1) ML24197A2012024-07-15015 July 2024 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000282/2024004 L-PI-24-036, – Preparation and Scheduling of Operator Licensing Examinations2024-06-28028 June 2024 – Preparation and Scheduling of Operator Licensing Examinations IR 05000282/20240102024-06-28028 June 2024 Comprehensive Engineering Team Inspection Report 05000282/2024010 and 05000306/2024010 ML24158A5912024-06-0606 June 2024 CFR 50.46 LOCA Annual Report L-PI-24-031, Independent Spent Fuel Storage Installation, Supplement to License Amendment Request to Revise Independent Spent Fuel Storage Installation (ISFSI) License Conditions 23(a), 24(A)(2), and 24(B)(2)2024-06-0505 June 2024 Independent Spent Fuel Storage Installation, Supplement to License Amendment Request to Revise Independent Spent Fuel Storage Installation (ISFSI) License Conditions 23(a), 24(A)(2), and 24(B)(2) L-PI-24-014, License Amendment Request to Revise the Technical Specification Definition of Reactor Trip System (RTS) Response Time and Apply Response Time Testing to RTS Trip Functions with Time Delay Assumption2024-06-0303 June 2024 License Amendment Request to Revise the Technical Specification Definition of Reactor Trip System (RTS) Response Time and Apply Response Time Testing to RTS Trip Functions with Time Delay Assumption ML24155A1952024-05-31031 May 2024 Reactor Trip and Auto-Start Actuation of Auxiliary Feedwater Due to Loss of Suction to the 22 Main Feedwater Pump ML24155A1922024-05-31031 May 2024 Refueling Outage Unit 2 R33 Owners Activity Report for Class 1, 2, 3 and Mc Inservice Inspections ML24149A3712024-05-29029 May 2024 (Ping) - Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection ML24262A1992024-05-29029 May 2024 L-PI-24-018 PINGP 75 Day Letter L-PI-24-030, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.8.12024-05-22022 May 2024 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.8.1 ML24141A1292024-05-22022 May 2024 Northern States Power Company - Use of Encryption Software for Electronic Transmission of Safeguards Information ML24141A0452024-05-20020 May 2024 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection ML24128A2572024-05-16016 May 2024 ISFSI A13 Acceptance Letter IR 05000282/20240012024-05-15015 May 2024 Integrated Inspection Report 05000282/2024001 and 05000306/2024001 ML24130A2392024-05-0909 May 2024 2023 Annual Radioactive Effluent Report ML24130A2362024-05-0909 May 2024 Independent Spent Fuel Storage Installation - 2023 Annual Radiological Environmental Monitoring Program Report ML24071A1162024-05-0101 May 2024 Issuance of Amendment Nos. 244 and 232 Revise TS 3.7.8, Cooling Water (Cl) System ML24128A0882024-04-30030 April 2024 Submittal of Updated Safety Analysis Report (Usar), Revision 38 ML24089A2382024-04-29029 April 2024 Summary of Nuclear Property Insurance ML24121A0432024-04-29029 April 2024 Reactor Trip and Auto-Start Actuation of Auxiliary Feedwater Due to Loss of Suction to the 22 Main Feedwater Pump IR 05000282/20244012024-04-25025 April 2024 – Security Baseline Inspection Report 05000282/2024401 and 05000306/2024401 ML24100A8042024-04-24024 April 2024 – Alternative Request RR-09 for Safety Injection and Volume Control System Category C Check Valve Inservice Testing ML24114A0882024-04-23023 April 2024 Annual Report of Individual Monitoring for the Prairie Island Nuclear Generating Plant (PINGP) ML24113A1182024-04-12012 April 2024 NRC Letter Re NRC Office of Investigations Report No. 3-2023-004 ML24100A1212024-04-0909 April 2024 Submittal of Revised Pressure and Temperature Limits Report L-PI-24-012, Independent Spent Fuel Storage Installation - License Amendment Request: Revise Independent Spent Fuel Storage Installation (ISFSI) License Conditions 23(a), 24(A)(2), and 24(B)(2)2024-04-0202 April 2024 Independent Spent Fuel Storage Installation - License Amendment Request: Revise Independent Spent Fuel Storage Installation (ISFSI) License Conditions 23(a), 24(A)(2), and 24(B)(2) ML24093A2832024-04-0202 April 2024 Nuclear Material Transaction Report ML24089A2402024-03-29029 March 2024 Guarantee of Payment of Deferred Premiums ML24060A1232024-03-27027 March 2024 to Request 1-RR-5-10 and 2-RR-5-10 Regarding Reactor Pressure Vessel Welds and Nozzle Welds ML24081A1532024-03-21021 March 2024 Reactor Trip, Auxiliary Feedwater and Emergency Service Water System Actuation Due to Electrical Transient in DC Control Power Cables ML24262A1512024-03-15015 March 2024 L-PI-24-011 150 Day Letter 2024 PINGP ILT NRC Exam ML24010A0582024-03-0505 March 2024 Amendment No. 12 to Materials License No. Special Nuclear Material-2506 for the Prairie Island Independent Spent Fuel Storage Installation L-PI-24-004, Independent Spent Fuel Storage Installation - Annual Effluent Report, January Through December 20232024-02-29029 February 2024 Independent Spent Fuel Storage Installation - Annual Effluent Report, January Through December 2023 IR 05000282/20230062024-02-28028 February 2024 Annual Assessment Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report 05000282/2023006 and 05000306/2023006) ML24088A1102024-02-25025 February 2024 Fairbanks Morse (Fm) Part 21 Notification Report Number 23-01 Re Asco Stainless Steel Solenoid Valves L-PI-24-009, Response to Request for Additional Information Prairie Island Nuclear Generating Plant, Unit 2, Alternative RR-09 Safety Injection System and Volume Control System Category C Check Valve Quarterly Testing2024-02-13013 February 2024 Response to Request for Additional Information Prairie Island Nuclear Generating Plant, Unit 2, Alternative RR-09 Safety Injection System and Volume Control System Category C Check Valve Quarterly Testing ML24040A1712024-02-0909 February 2024 Interim Report of a Potential Deviation or Failure to Comply Associated with Bentley Systems Incorporated Autopipe Software IR 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) 2024-09-23
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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