|
|
Line 35: |
Line 35: |
|
| |
|
| ==Enclosures:== | | ==Enclosures:== |
| 1. Description of Information Requested and Transmitted 2. CD containing USACE FHR spreadsheets, plots, and GIS files 3. Hydrographs and Inundation Maps cc w/o encls: Distribution via Listserv OFFICIAL USE ONLY - SECURITY-RELATED INFORMATION K Davison OFFICIAL USE ONLY - SECURITY-RELATED INFORMATION If you have any questions, please contact me at (301) 415-2915 or by e-mail at Victor.Hall@nrc.gov. | | : 1. Description of Information Requested and Transmitted 2. CD containing USACE FHR spreadsheets, plots, and GIS files 3. Hydrographs and Inundation Maps cc w/o encls: Distribution via Listserv |
| Sincerely, /RA/
| |
| Victor Hall, Senior Project Manager Hazards Management Branch Japan Lessons-Learned Division Office of Nuclear Reactor Regulation Docket Nos. 50-282, and 50-306
| |
|
| |
|
| ==Enclosures:==
| | Pkg: ML15296A361 Letter: ML15296A349 *via e-mail OFFICE NRR/JLD/JHMB/PM NRR/JLD/JHMB/LA NRR/JLD/JHMB/BC NAME VHall SLent MShams DATE 10/26/15 11/4/15 11/15/15 OFFICE NRO/DSEA/RHM1/BC NRR/JLD/JHMB/PM NAME CCook ARiveraVarona for* VHall DATE 11/2/15 11/18/15 OFFICIAL USE ONLY - SECURITY-RELATED INFORMATION Enclosure 1 OFFICIAL USE ONLY - SECURITY-RELATED INFORMATION Licensee Requested Information for Prairie Island Nuclear Power Plant: Licensee Requested Information USACE Provided Information - Filename in Enclosure 2 Flow and Stage Hydrographs (River miles 902.7, 900.6, and 899.3) Appendix E - Hydrographs.pdf1 Hydrographs - Excel Format.xls1 Maximum flow velocities at four cross sections Max Water Surfaces and Depths.xls1 GIS shapefile of all cross sections between river miles 902.7 and 894.4 Prairie Island RAS XS Locations2 Maximum water surface elevation at all cross sections between river miles 902.7 and 894.4 Max Water Surfaces and Depths.xls1 Average water depth (or top width and flow area) at each cross section between river miles 902.7 and 894.4 Max Water Surfaces and Depths.xls1 GIS shapefile of limits of inundation between river miles 902.7 and 894.4 Prairie Island_Inundation2 1 Monticello Nuclear Power Plant and Prairie Island Nuclear Power Plant information are provided in the same pdf file and Excel spreadsheets. 2 GIS files include files with .shp, .shx, .dbf, and .prj extensions.}} |
| 1. Description of Information Requested and Transmitted 2. CD containing USACE FHR spreadsheets, plots, and GIS files 3. Hydrographs and Inundation Maps cc w/o encls: Distribution via Listserv DISTRIBUTION: PUBLIC (LETTER ONLY) JHMB R/F RidsNrrDorlLpl3-1 Resource RidsNrrLASLent Resource RidsNrrPMPrairieIsland Resource RidsNsirDspRsps Resource RidsRgn3MailCenter Resource BHarvey, NRO CCook, NRO MShams, NRR KSee, NRO ACampbell NRO PChaput, NRO VHall, NRR ADAMS Accession Nos.: Pkg: ML15296A361 Letter: ML15296A349 *via e-mail OFFICE NRR/JLD/JHMB/PM NRR/JLD/JHMB/LA NRR/JLD/JHMB/BC NAME VHall SLent MShams DATE 10/26/15 11/4/15 11/15/15 OFFICE NRO/DSEA/RHM1/BC NRR/JLD/JHMB/PM NAME CCook ARiveraVarona for* VHall DATE 11/2/15 11/18/15 OFFICIAL RECORD COPY OFFICIAL USE ONLY - SECURITY-RELATED INFORMATION Enclosure 1 OFFICIAL USE ONLY - SECURITY-RELATED INFORMATION Licensee Requested Information for Prairie Island Nuclear Power Plant: Licensee Requested Information USACE Provided Information - Filename in Enclosure 2 Flow and Stage Hydrographs (River miles 902.7, 900.6, and 899.3) Appendix E - Hydrographs.pdf1 Hydrographs - Excel Format.xls1 Maximum flow velocities at four cross sections Max Water Surfaces and Depths.xls1 GIS shapefile of all cross sections between river miles 902.7 and 894.4 Prairie Island RAS XS Locations2 Maximum water surface elevation at all cross sections between river miles 902.7 and 894.4 Max Water Surfaces and Depths.xls1 Average water depth (or top width and flow area) at each cross section between river miles 902.7 and 894.4 Max Water Surfaces and Depths.xls1 GIS shapefile of limits of inundation between river miles 902.7 and 894.4 Prairie Island_Inundation2 1 Monticello Nuclear Power Plant and Prairie Island Nuclear Power Plant information are provided in the same pdf file and Excel spreadsheets. 2 GIS files include files with .shp, .shx, .dbf, and .prj extensions.
| |
| }} | |
Revision as of 14:38, 1 June 2018
Letter Sequence Other |
---|
|
|
MONTHYEARL-MT-14-024, L-MT-14-024, Request for NRC Assistance to Obtain Information on Dams from the Us Army Corps of Engineers (Usace)2014-03-0505 March 2014 L-MT-14-024, Request for NRC Assistance to Obtain Information on Dams from the Us Army Corps of Engineers (Usace) Project stage: Request L-PI-14-023, Request for NRC Assistance to Obtain Information on Dams from the U.S. Army Corps of Engineers2014-03-0505 March 2014 Request for NRC Assistance to Obtain Information on Dams from the U.S. Army Corps of Engineers Project stage: Request ML14205A5242014-07-24024 July 2014 August5, 2014 Notice of Forthcoming Closed Meeting to Discuss Dam Failure Analysis for Monticello Nuclear Generating Plant and Prairie Island Nuclear Generating Plant, Units 1 and 2 Project stage: Meeting ML14220A2832014-09-0808 September 2014 Summary of August 5, 2014, Closed Meeting Between Representatives of the U.S. Army Corps of Engineers, NRC, and Northern States Power Company - Minnesota to Discuss Flooding Analysis Associated with Monticello and Prairie Island Nuclear Gen Project stage: Meeting ML15181A0202015-07-0101 July 2015 July 9, 2015 Forthcoming Closed Meeting to Discuss Dam Failure Analysis for Monticello Nuclear Generating Plant and Prairie Island Nuclear Generating Plant, Units 1 and 2 Project stage: Meeting ML15271A2072015-10-0202 October 2015 July 9, 2015 Summary of Closed Meeting Between Representatives of the U.S. Army Corps of Engineers, U.S, Nuclear Regulatory Commission and Northern States Power Company- Minnesota to Discuss Flood Analysis Associated with Monticello Nuclear Project stage: Meeting ML15324A3712015-11-18018 November 2015 Transmittal of U.S. Army Corps of Engineers Flood Hazard Reevaluation Information (Public) Project stage: Other 2014-09-08
[Table View] |
|
---|
Category:Letter
MONTHYEARIR 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 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 2024-09-27
[Table view] |
Text
OFFICIAL USE ONLY - SECURITY-RELATED INFORMATION OFFICIAL USE ONLY - SECURITY-RELATED INFORMATION November 18, 2015 Mr. Kevin K. Davison Site Vice President Northern States Power Company - Minnesota Prairie Island Nuclear Generating Plant 1717 Wakonade Drive East Welch, MN 55089-9642
SUBJECT:
PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 - TRANSMITTAL OF U.S. ARMY CORPS OF ENGINEERS FLOOD HAZARD REEVALUATION INFORMATION (TAC NOS. MF3697 AND MF3698)
Dear Mr. Davison:
The purpose of this letter is to transmit the U.S. Army Corps of Engineers (USACE) portion of the Prairie Island Nuclear Generating Plant, Units 1 and 2 flood hazard reevaluation (FHR) associated with the assessment of flood hazards due to flooding in streams and rivers, including potential site flooding due to dam failure. By letters dated May 5, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML14065A112 and ML14064A291), Northern States Power Company - Minnesota (the licensee), doing business as Xcel Energy (Xcel), requested assistance from the U.S. Nuclear Regulatory Commission (NRC) in obtaining information from the USACE to support Xcel's development of a report documenting the FHR in response to the March 12, 2012, request for information (ADAMS Accession No. ML12073A348). The NRC staff held meetings to discuss the details of the information being provided by USACE with Xcel and the USACE on the following dates:
- July 9, 2015 (summary at ADAMS Accession No. ML15271A207) These meetings were closed to the public due to the discussion of security-related information. Enclosures 2 and 3 to this letter contain the results of the USACE flood hazard reevaluation and is non-public for security-related information. Xcel needs to consider the USACE results for Prairie Island as part of its flood hazard reevaluation report, which is due to the NRC within 180 days of this letter (May 16, 2016). The information contained in the enclosures was developed in accordance with Japan Lessons-Learned Directorate (JLD) interim staff guidance (ISG) JLD-ISG-2013-01, "Interim Staff Guidance For Assessment of Flooding Hazards Due to Dam Failure," Revision 0, dated July 29, 2013 (ADAMS Accession No. ML13151A153), and on the USACE knowledge of the river system.
Enclosures two and three to this letter contain Security-Related Information. When separated from Enclosures two and three, this letter and Enclosure one are DECONTROLLED.
OFFICIAL USE ONLY - SECURITY-RELATED INFORMATION K. Davison OFFICIAL USE ONLY - SECURITY-RELATED INFORMATION If you have any questions, please contact me at (301) 415-2915 or by e-mail at Victor.Hall@nrc.gov.
Sincerely, /RA/
Victor Hall, Senior Project Manager Hazards Management Branch Japan Lessons-Learned Division Office of Nuclear Reactor Regulation Docket Nos. 50-282 and 50-306
Enclosures:
- 1. Description of Information Requested and Transmitted 2. CD containing USACE FHR spreadsheets, plots, and GIS files 3. Hydrographs and Inundation Maps cc w/o encls: Distribution via Listserv
Pkg: ML15296A361 Letter: ML15296A349 *via e-mail OFFICE NRR/JLD/JHMB/PM NRR/JLD/JHMB/LA NRR/JLD/JHMB/BC NAME VHall SLent MShams DATE 10/26/15 11/4/15 11/15/15 OFFICE NRO/DSEA/RHM1/BC NRR/JLD/JHMB/PM NAME CCook ARiveraVarona for* VHall DATE 11/2/15 11/18/15 OFFICIAL USE ONLY - SECURITY-RELATED INFORMATION Enclosure 1 OFFICIAL USE ONLY - SECURITY-RELATED INFORMATION Licensee Requested Information for Prairie Island Nuclear Power Plant: Licensee Requested Information USACE Provided Information - Filename in Enclosure 2 Flow and Stage Hydrographs (River miles 902.7, 900.6, and 899.3) Appendix E - Hydrographs.pdf1 Hydrographs - Excel Format.xls1 Maximum flow velocities at four cross sections Max Water Surfaces and Depths.xls1 GIS shapefile of all cross sections between river miles 902.7 and 894.4 Prairie Island RAS XS Locations2 Maximum water surface elevation at all cross sections between river miles 902.7 and 894.4 Max Water Surfaces and Depths.xls1 Average water depth (or top width and flow area) at each cross section between river miles 902.7 and 894.4 Max Water Surfaces and Depths.xls1 GIS shapefile of limits of inundation between river miles 902.7 and 894.4 Prairie Island_Inundation2 1 Monticello Nuclear Power Plant and Prairie Island Nuclear Power Plant information are provided in the same pdf file and Excel spreadsheets. 2 GIS files include files with .shp, .shx, .dbf, and .prj extensions.