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MONTHYEARL-PI-12-102, Supplement to License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactors - Submittal of Lnternal Flooding Peer Review Final Results and Revised Total Plant Risk Values2012-11-0808 November 2012 Supplement to License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactors - Submittal of Lnternal Flooding Peer Review Final Results and Revised Total Plant Risk Values Project stage: Supplement ML12335A1832012-11-29029 November 2012 11/29/12 E-mail, Acceptance Review Questions Regarding NFPA 805 License Amendment Request Project stage: Acceptance Review L-PI-12-117, Supplement to License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactors - Response to Acceptance Review Questions2012-12-18018 December 2012 Supplement to License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactors - Response to Acceptance Review Questions Project stage: Supplement L-PI-13-044, Commitment to Submit a Supplement to the PINGP NFPA 805 License Amendment Request2013-05-0303 May 2013 Commitment to Submit a Supplement to the PINGP NFPA 805 License Amendment Request Project stage: Supplement ML13282A5382013-10-0909 October 2013 Status of Review of National Fire Protection Association Standard 805 Application Project stage: Approval L-PI-13-093, NFPA 805 License Amendment Request- Milestone Schedule for Submittal of Supplement2013-10-17017 October 2013 NFPA 805 License Amendment Request- Milestone Schedule for Submittal of Supplement Project stage: Supplement ML15062A1502015-03-0303 March 2015 NRR E-mail Capture - Prairie Island Nuclear Plant, Units 1 and 2 - NFPA 805 Pre-Audit Draft Requests for Additional Information Project stage: Draft RAI ML15089A1572015-03-30030 March 2015 NRR E-mail Capture - Prairie Island Nuclear Generating Plant, Units 1 and 2 - NFPA 805 Requests for Additional Information and Response Timeline Project stage: RAI L-PI-15-041, License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactors - Response to Request for Additional Information2015-05-28028 May 2015 License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactors - Response to Request for Additional Information Project stage: Response to RAI L-PI-15-052, License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactors - Response to Request for Additional Information - 90-Day Responses2015-06-19019 June 2015 License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactors - Response to Request for Additional Information - 90-Day Responses Project stage: Response to RAI ML15243A4092015-08-28028 August 2015 NRR E-mail Capture - Prairie Island Nuclear Generating Plant - Final Requests for Additional Information (Second Round) from Apla LAR to Adopt NFPA 805 Project stage: RAI ML15243A4102015-08-28028 August 2015 NRR E-mail Capture - Prairie Island Nuclear Generating Plant - Final Requests for Additional Information (Fire Modeling - Second Round) LAR to Adopt NFPA 805 Project stage: RAI L-PI-15-059, License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Information (PRA-Second Round)2015-10-22022 October 2015 License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Information (PRA-Second Round) Project stage: Request L-PI-16-004, License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactors- Response to Request for Additional Information2016-01-20020 January 2016 License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactors- Response to Request for Additional Information Project stage: Response to RAI L-PI-16-005, License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactors - Response to Request for Additional Information2016-05-24024 May 2016 License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactors - Response to Request for Additional Information Project stage: Response to RAI 2015-10-22
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Category:Letter
MONTHYEARIR 05000282/20240032024-11-13013 November 2024 Integrated Inspection Report 05000282/2024003, 05000306/2024003 & 07200010/2024001 ML24310A1682024-11-0505 November 2024 Core Operating Limits Report (COLR) for Cycle 34, Revision 0 ML24298A0552024-10-30030 October 2024 Response to Alternative RR-10, Auxiliary Feedwater Valve Testing IR 05000282/20244032024-10-25025 October 2024 – Security Baseline Inspection Report 05000282/2024403 and 05000306/2024403 05000282/LER-2024-001-01, Auxiliary Building Special Ventilation System Inoperable During Movement of Irradiated Fuel Assemblies2024-10-22022 October 2024 Auxiliary Building Special Ventilation System Inoperable During Movement of Irradiated Fuel Assemblies L-PI-24-044, Application to Revise Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program2024-10-21021 October 2024 Application to Revise Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program ML24277A1012024-10-0303 October 2024 Closure of Interim Report of a Potential Deviation or Failure to Comply Associated with Bentley Systems Incorporated Autopipe Software ML24221A3622024-09-27027 September 2024 Issuance of Amendment Nos. 245 and 233 Revise Technical Specification 3.8.1, AC Sources-Operating, Surveillance Requirement 3.8.1.2, Note 3 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 IR 05000282/20240102024-06-28028 June 2024 Comprehensive Engineering Team Inspection Report 05000282/2024010 and 05000306/2024010 L-PI-24-036, – Preparation and Scheduling of Operator Licensing Examinations2024-06-28028 June 2024 – Preparation and Scheduling of Operator Licensing Examinations 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 ML24155A1922024-05-31031 May 2024 Refueling Outage Unit 2 R33 Owners Activity Report for Class 1, 2, 3 and Mc Inservice Inspections 05000306/LER-2024-001-01, Reactor Trip and Auto-Start Actuation of Auxiliary Feedwater Due to Loss of Suction to the 22 Main Feedwater Pump2024-05-31031 May 2024 Reactor Trip and Auto-Start Actuation of Auxiliary Feedwater Due to Loss of Suction to the 22 Main Feedwater Pump 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 ML24130A2362024-05-0909 May 2024 Independent Spent Fuel Storage Installation - 2023 Annual Radiological Environmental Monitoring Program Report ML24130A2392024-05-0909 May 2024 2023 Annual Radioactive Effluent 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 05000306/LER-2024-001, Reactor Trip and Auto-Start Actuation of Auxiliary Feedwater Due to Loss of Suction to the 22 Main Feedwater Pump2024-04-29029 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 ML24093A2832024-04-0202 April 2024 Nuclear Material Transaction 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) 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 05000282/LER-2023-001-01, Reactor Trip, Auxiliary Feedwater and Emergency Service Water System Actuation Due to Electrical Transient in DC Control Power Cables2024-03-21021 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 2024-09-27
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II Xcel Energy Prairie Island Nuclear Generating Plant 1717 Wakonade Drive East Welch, MN 55089 May 3,2013 L-PI-13-044 10 CFR 50.90 u.s. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Prairie Island Nuclear Generating Plant Units 1 and 2 Dockets 50-282 and 50-306 Renewed License Nos. DPR-42 and DPR-60 Commitment to Submit a Supplement to the PINGP NFPA 805 License Amendment Request (TAC Nos. ME9734 and ME9735) References: 1. NSPM letter, J.P. Sorensen to NRC Document Control Desk, "License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactors," L-PI-12-089, dated September 28,2012, ADAMS Accession No. ML 12278A405. 2. NRC letter, T.J. Wengert to J.E. Lynch (NSPM), "Prairie Island Nuclear Generating Plant, Units 1 and 2 -Acceptance for Review of License Amendment Request for National Fire Protection Association Standard NFPA 805 (TAC Nos. ME9734 and ME9735)," dated January 2, 2013, ADAMS Accession No. ML 13002A209. In Reference 1, Northern States Power Company, a Minnesota Corporation (NSPM), doing business as Xcel Energy, submitted a License Amendment Request (LAR) to the Nuclear Regulatory Commission (NRC), to adopt National Fire Protection Association Standard 805 (NFPA 805) as the licensing basis standard for the fire protection program at the Prairie Island Nuclear Generating Plant (PINGP). Supplemental information was provided in letters dated November 8,2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 12314A144) and December 18,2012 (ADAMS Accession No. ML 12354A464). The LAR was accepted by the NRC for further review in Reference 2.
Document Control Desk Page 2 During internal reviews in preparation for the NRC Audit of the PINGP NFPA 805 LAR, NSPM identified a number of issues with the Fire Probabilistic Risk Assessment (PRA). Several of these issues were determined to affect the risk values identified in Reference 1 and in the December 18, 2012 supplement (ADAMS Accession No. ML 12354A464). NSPM discussed these issues informally with the NRC Staff during telephone conferences on February 21 and March 18, 2013. Subsequent to these discussions, the NRC informed NSPM that the NFPA 805 Audit would be postponed. After further review, NSPM has determined that a revision is required to the PINGP Fire PRA. The results of this PRA revision will be provided in a supplement to the LAR by May 1,2014. This letter is submitted in accordance with 10 CFR 50.90. The information provided in this letter does not impact the conclusions of the No Significant Hazards Evaluation or Environmental Considerations Evaluation presented in the Reference 1 submittal. In accordance with 10 CFR 50.91, NSPM is notifying the State of Minnesota by transmitting a copy of this letter to the designated State Official. If there are any questions or if additional information is needed, please contact Gene Eckholt at 651-388-1121 x4137. Summary of Commitments This letter contains the following new commitment: NSPM commits to provide a supplement to the NFPA 805 LAR with revised Fire PRA results by May 1, 2014. I declare under penalty of perjury that the foregoing is true and correct. Executed on 5/3 /;3 /£hvL Site Vice President, Prairie Island Nuclear Generating Plant Northern States Power Company -Minnesota cc: Administrator, Region III, USNRC NRR Project Manager, PINGP, USNRC Resident Inspector, PINGP, USNRC Minnesota Department of Commerce