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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: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
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARL-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 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 ML23262B0372023-09-19019 September 2023 Response to NRC Request for Additional Information Regarding the 2023 Monticello and Prairie Island Plant Decommissioning Funding Status Reports L-PI-22-034, Response to RAI, Alternative RR-08 Related to Pressure Isolation Valve Monitoring and Testing2022-07-14014 July 2022 Response to RAI, Alternative RR-08 Related to Pressure Isolation Valve Monitoring and Testing ML22161A9152022-06-10010 June 2022 and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Response to a Request for Additional Information Xcel Energy Amendment Request to Create a Common Emergency Plan and Emergency Operations. L-PI-22-033, Response to Request for Additional Information Prairie Island Nuclear Generating Plant, Units 1 and 2, Amendment to Adopt 24-Month Operating Cycles2022-06-10010 June 2022 Response to Request for Additional Information Prairie Island Nuclear Generating Plant, Units 1 and 2, Amendment to Adopt 24-Month Operating Cycles L-PI-21-047, Response to Request for Additional Information 24-Month Cycle Amendment Prairie Island Nuclear Generating Plant, Units 1 and 22021-12-0707 December 2021 Response to Request for Additional Information 24-Month Cycle Amendment Prairie Island Nuclear Generating Plant, Units 1 and 2 L-PI-21-045, Response to Request for Additional Information Cooling Water System License Amendment Request2021-11-0404 November 2021 Response to Request for Additional Information Cooling Water System License Amendment Request L-PI-21-032, Response to Request for Additional Information Amendment Request to Adopt TSTF-471 and 571-T for Prairie Island2021-09-30030 September 2021 Response to Request for Additional Information Amendment Request to Adopt TSTF-471 and 571-T for Prairie Island L-PI-20-026, Response to Request for Additional Information: License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiativ2020-09-0101 September 2020 Response to Request for Additional Information: License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4 L-PI-20-023, Independent Spent Fuel Storage Installation, Response to Request for Additional Information: License Amendment Request to Expand the Storage Capacity of the Independent Spent Fuel Storage Installation (ISFSI)2020-06-10010 June 2020 Independent Spent Fuel Storage Installation, Response to Request for Additional Information: License Amendment Request to Expand the Storage Capacity of the Independent Spent Fuel Storage Installation (ISFSI) ML20045E8942020-02-14014 February 2020 Response to a Request for Additional Information for Proposed 10 CFR 50.55a(z)(2) Alternatives to Utilize ASME Code Case N-786-3, Alternative Requirements for Sleeve Reinforcement of Class 2 and 3 Moderate-Energy Carbon Steel Piping, and AS ML20127J0002019-11-0707 November 2019 Xcel Reply to PIIC Expansion Application L-PI-19-037, Response to Request for Additional Information: 10 CFR 50.55a Requests Nos. 1-RR-5-10 and 2-RR-5-10, Proposed Alternative to Reactor Vessel Inservice Inspection (ISI) Intervals2019-09-16016 September 2019 Response to Request for Additional Information: 10 CFR 50.55a Requests Nos. 1-RR-5-10 and 2-RR-5-10, Proposed Alternative to Reactor Vessel Inservice Inspection (ISI) Intervals L-PI-19-029, Supplement to Response to Request for Additional Information: Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components For...2019-08-0505 August 2019 Supplement to Response to Request for Additional Information: Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components For... L-PI-19-014, Response to Request for Additional Information: Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2019-04-29029 April 2019 Response to Request for Additional Information: Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors L-PI-18-063, Response to Request for Additional Information: Revise License Condition Associated with Implementation of NFPA 8052018-12-0606 December 2018 Response to Request for Additional Information: Revise License Condition Associated with Implementation of NFPA 805 L-PI-18-051, Response to Request for Additional Information: Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program2018-09-17017 September 2018 Response to Request for Additional Information: Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program L-PI-18-038, Supplement to License Amendment Request to Revise License Condition Associated with Implementation of NFPA 8052018-07-10010 July 2018 Supplement to License Amendment Request to Revise License Condition Associated with Implementation of NFPA 805 ML18131A2232018-05-11011 May 2018 Prairie and Monticello - Response to Request for Additional Information Regarding Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Di L-PI-17-042, Response to Request for Additional Information Regarding License Amendment Request to Revise the NDE Inspection Interval for Special Lifting Devices2017-11-0606 November 2017 Response to Request for Additional Information Regarding License Amendment Request to Revise the NDE Inspection Interval for Special Lifting Devices ML17279A1212017-10-0404 October 2017 Enclosure 2 to L-PI-17-041, Westinghouse-Prepared RAI Responses CE-17-3, Rev. 1, Attachment 2 and Enclosure 3, Marked-Up Technical Specification Page 4.0-7 L-PI-17-035, License Amendment Request to Revise the Emergency Action Level (EAL) Scheme - Supplement and Response to Requests for Additional Information2017-09-27027 September 2017 License Amendment Request to Revise the Emergency Action Level (EAL) Scheme - Supplement and Response to Requests for Additional Information L-PI-17-032, Response to Request for Additional Information Regarding License Amendment Request to Revise Emergency Plan Staff Augmentation Response Times2017-09-20020 September 2017 Response to Request for Additional Information Regarding License Amendment Request to Revise Emergency Plan Staff Augmentation Response Times L-PI-17-007, Response to Request for Additional Information on License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactors2017-03-0606 March 2017 Response to Request for Additional Information on License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactors L-PI-17-002, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.8.7 to Remove Non-Conservative Required Action2017-02-16016 February 2017 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.8.7 to Remove Non-Conservative Required Action L-PI-16-100, Response to NRC Request for Information - License Amendment Request for Spent Fuel Pool Criticality Technical Specification Changes2017-02-16016 February 2017 Response to NRC Request for Information - License Amendment Request for Spent Fuel Pool Criticality Technical Specification Changes L-PI-16-090, Response to Request for Additional Information on License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactors2016-12-14014 December 2016 Response to Request for Additional Information on License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactors ML16351A2102016-12-13013 December 2016 External Flooding Assessment Focused Evaluation. (Redacted) ML16288A0972016-10-14014 October 2016 and Monticello - Response to Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools L-PI-16-076, Supplement to the Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 2, Flood Hazard Reevaluation Report2016-09-29029 September 2016 Supplement to the Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 2, Flood Hazard Reevaluation Report ML16279A4792016-09-29029 September 2016 Flood Hazard Reevaluation Report - Response to Requested Information L-PI-16-067, License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactors- Response to Request for Additional Information2016-08-17017 August 2016 License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactors- Response to Request for Additional Information L-PI-16-063, Seventh Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events2016-08-17017 August 2016 Seventh Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events 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 ML16144A8062016-05-23023 May 2016 Supplement to License Amendment Request for Spent Fuel Pool Criticality Technical Specification Changes: Response to RAI-2 (Enclosure 1) & Marked-Up Technical Specification Page (Enclosure 2) L-PI-16-040, Supplement to License Amendment Request for Spent Fuel Pool Criticality Technical Specification Changes: Westinghouse-Prepared Response to RAI, CE-16-237, Attachment 2 (Enclosure 4)2016-05-23023 May 2016 Supplement to License Amendment Request for Spent Fuel Pool Criticality Technical Specification Changes: Westinghouse-Prepared Response to RAI, CE-16-237, Attachment 2 (Enclosure 4) ML16133A0412016-05-0909 May 2016 Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 2, Flood Hazard Reevaluation Report L-08-001, Response to Requests for Additional Information - License Amendment Request to Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Revision 2, Using the Consolidated..2016-04-14014 April 2016 Response to Requests for Additional Information - License Amendment Request to Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Revision 2, Using the Consolidated.. L-PI-16-029, Response to Requests for Additional Information - License Amendment Request to Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Revision 2,,Using the Consolidated..2016-03-31031 March 2016 Response to Requests for Additional Information - License Amendment Request to Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Revision 2,,Using the Consolidated.. 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 L-PI-16-001, Enclosure 2: Responses to Open and Pending Items from the NRC Audit Report2016-01-14014 January 2016 Enclosure 2: Responses to Open and Pending Items from the NRC Audit Report L-PI-15-105, License Amendment Request (LAR) to Revise Technical Specifications (TS) to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process - Response to Request..2015-12-30030 December 2015 License Amendment Request (LAR) to Revise Technical Specifications (TS) to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process - Response to Request.. 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 L-PI-14-113, Updated Final Response to NRC Request for Information Per 10CFR50.54(f) Re Seismic Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2015-01-16016 January 2015 Updated Final Response to NRC Request for Information Per 10CFR50.54(f) Re Seismic Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident 2024-01-02
[Table view] |
Text
Security-Related Information - Withhold Under 10 CFR 2.390(d)(1)
(l Xcel Energy~ Prairie Island Nuclear Generating Plant 1717 Wakonade Drive East Welch, MN 55089 May 9, 2016 L-Pl-16-039 10 CFR 50.54(f)
U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Prairie Island Nuclear Generating Plant Units 1 and 2 Docket Numbers 50-282 and 50-306 Renewed Facility Operating License Nos. DPR-42 and DPR-60 Prairie Island Nuclear Generating Plant, Units 1*and 2, Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 2, Flood Hazard Reevaluation Report
References:
- 1. NRG Letter, "Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accid~nt;"
dated March 12, 2012 (ADAMS Accession No. ML12056A046)
- 2. NRG Letter, "Prioritization of Response Due Dates for Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Flooding Hazard Reevaluations for Recommendations 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident," dated May 11, 2012 (ADAMS Accession No. ML12097A510)
- 3. NSPM Letter L-Pl-14-023 from K. Davison to Document Control Desk (NRC),
"Request for NRC Assistance to Obtain Information on Dams from the U.S. Army Corps of Engineers (USAGE)," dated March 5, 2014 (ADAMS Accession No. ML14064A291)
Enclosure 1 contains Security.-Related Information. When separated from Enclosure 1, this letter and Enclosure 2 are decontrolled.
Security-Related Information - Withhold Under 10 CFR 2.390(d)(1)
Document Control Desk Page2
- 4. NSPM Letter L-Pl-14-024 from S. Sharp to Document Control Desk (NRC),
"Extension Request Regarding the Flooding Hazard Reevaluation Report
- Required by NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendation 2.1, Flooding, of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident,"
dated March 10, 2014 (ADAMS Accession No. ML14069A544) *
- 5. NRC Letter, "Prairie lsla.nd Nuclear Generating Plant, Units 1 and 2 - Relaxation of Response Due Date Regarding Flooding Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Review of the Insights from the Fukushima Dai-ichi Accident (TAC Nos. MF3629 and MF3630)," dated July 29, 2014 (ADAMS Accession No. ML14171A166)
- 6. NRC Letter, "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)," dated November 18, 2015 (ADAMS Accession No. ML15296A361 (Public Version ML15296A371)) . .
On March 12, 2012, the NRC issued Reference 1, which included a request for information associated with Near-Term Task Force (NTTF) Recommendation 2.1 for flooding. Enclosure 2 of Reference 1 addresses the Requested Information and Required Response. The NRC Staff.requested licensees to perform a flood hazard reevaluation (Requested Information Item 1) and to provide a final report documenting the results in accordance with the NRC's prioriti?ation plan (Required Response Item 2).
On May 11, 2012, the NRC issued the prioritization plan (Reference 2). Reference 2, , identified Prairie Island Nuclear Generating Plant (PINGP), Units 1 and 2, as a Category 2 site requiring a response by March 12, 2014.
By the Reference 3 letter, Northern States Power Company, a Minnesota corporation (NSPM), d/b/a Xcel Energy, requested NRC assistance to obtain information needed to complete the Flood Hazard Reevaluation Report (FHRR) for PINGP from the United States Army Corps of Engineers (USAGE). NSPM requested that NRC act as interface between the USAGE and NSPM to obtain the necessary information. In the Reference 4 letter, NSPM requested an extension for the completion and submission of the FHRR from March 12, 2014 to within ten months of receiving the USACE's final information ..
The NRC revised the required response date (Reference 5) for the PINGP FHRR to six months after NSPM received the USAGE final analysis. The NRC transmitted the USAGE flood hazard information necessary for NSPM to complete the FHRR for PINGP in a letter dated November 18, 2015 (Reference 6). In the Reference 6 letter, the NRC identified that the PINGP FHRR is due by May 16, 2016.
The purpose of this letter is to provide the FHRR for PINGP, Units 1 and 2. The PINGP FHRR is enclosed. Direct responses to the Reference 1, Enclosure 2, Requested
Document Control Desk Page 3 Information, Item 1, are included in Appendix 1 of the PINGP FHRR. No interim actions are necessary. of this letter is being submitted as containing "Security-Related Information
- Withhold under 10 CFR 2.390:" NSPM hereby requests that Enclosure 1 be withheld from public disclosure in accordance with the provisions of 10 CFR 2.390. A redacted version of Enclosure 1 is provided in Enclosure 2.
Please contact Lynne Gunderson, Licensing Engineer, at 651-267-7421, if additional information or clarification is required.
Summary of Commitments This letter makes no new commitments and no .revisions to existing commitments.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on May 9, 2016.
~~
Scott Northard .
Acting Site Vice President, Prairie Island Nuclear Generating Plant Northern States Power Company - Minnesota Enclosures (2) cc: Administrator, Region Ill, USNRC Project Manager, Prairie Island Nuclear Generating Plant, USNRC Resident Inspector, Prairie Island Nuclear Generating Plant, USNRC
Security-Related Information - Withhold Under 10 CFR 2.390(d)(1)
(l Xcel Energy~ Prairie Island Nuclear Generating Plant 1717 Wakonade Drive East Welch, MN 55089 May 9, 2016 L-Pl-16-039 10 CFR 50.54(f)
U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Prairie Island Nuclear Generating Plant Units 1 and 2 Docket Numbers 50-282 and 50-306 Renewed Facility Operating License Nos. DPR-42 and DPR-60 Prairie Island Nuclear Generating Plant, Units 1*and 2, Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 2, Flood Hazard Reevaluation Report
References:
- 1. NRG Letter, "Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accid~nt;"
dated March 12, 2012 (ADAMS Accession No. ML12056A046)
- 2. NRG Letter, "Prioritization of Response Due Dates for Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Flooding Hazard Reevaluations for Recommendations 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident," dated May 11, 2012 (ADAMS Accession No. ML12097A510)
- 3. NSPM Letter L-Pl-14-023 from K. Davison to Document Control Desk (NRC),
"Request for NRC Assistance to Obtain Information on Dams from the U.S. Army Corps of Engineers (USAGE)," dated March 5, 2014 (ADAMS Accession No. ML14064A291)
Enclosure 1 contains Security.-Related Information. When separated from Enclosure 1, this letter and Enclosure 2 are decontrolled.
Security-Related Information - Withhold Under 10 CFR 2.390(d)(1)
Document Control Desk Page2
- 4. NSPM Letter L-Pl-14-024 from S. Sharp to Document Control Desk (NRC),
"Extension Request Regarding the Flooding Hazard Reevaluation Report
- Required by NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendation 2.1, Flooding, of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident,"
dated March 10, 2014 (ADAMS Accession No. ML14069A544) *
- 5. NRC Letter, "Prairie lsla.nd Nuclear Generating Plant, Units 1 and 2 - Relaxation of Response Due Date Regarding Flooding Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Review of the Insights from the Fukushima Dai-ichi Accident (TAC Nos. MF3629 and MF3630)," dated July 29, 2014 (ADAMS Accession No. ML14171A166)
- 6. NRC Letter, "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)," dated November 18, 2015 (ADAMS Accession No. ML15296A361 (Public Version ML15296A371)) . .
On March 12, 2012, the NRC issued Reference 1, which included a request for information associated with Near-Term Task Force (NTTF) Recommendation 2.1 for flooding. Enclosure 2 of Reference 1 addresses the Requested Information and Required Response. The NRC Staff.requested licensees to perform a flood hazard reevaluation (Requested Information Item 1) and to provide a final report documenting the results in accordance with the NRC's prioriti?ation plan (Required Response Item 2).
On May 11, 2012, the NRC issued the prioritization plan (Reference 2). Reference 2, , identified Prairie Island Nuclear Generating Plant (PINGP), Units 1 and 2, as a Category 2 site requiring a response by March 12, 2014.
By the Reference 3 letter, Northern States Power Company, a Minnesota corporation (NSPM), d/b/a Xcel Energy, requested NRC assistance to obtain information needed to complete the Flood Hazard Reevaluation Report (FHRR) for PINGP from the United States Army Corps of Engineers (USAGE). NSPM requested that NRC act as interface between the USAGE and NSPM to obtain the necessary information. In the Reference 4 letter, NSPM requested an extension for the completion and submission of the FHRR from March 12, 2014 to within ten months of receiving the USACE's final information ..
The NRC revised the required response date (Reference 5) for the PINGP FHRR to six months after NSPM received the USAGE final analysis. The NRC transmitted the USAGE flood hazard information necessary for NSPM to complete the FHRR for PINGP in a letter dated November 18, 2015 (Reference 6). In the Reference 6 letter, the NRC identified that the PINGP FHRR is due by May 16, 2016.
The purpose of this letter is to provide the FHRR for PINGP, Units 1 and 2. The PINGP FHRR is enclosed. Direct responses to the Reference 1, Enclosure 2, Requested
Document Control Desk Page 3 Information, Item 1, are included in Appendix 1 of the PINGP FHRR. No interim actions are necessary. of this letter is being submitted as containing "Security-Related Information
- Withhold under 10 CFR 2.390:" NSPM hereby requests that Enclosure 1 be withheld from public disclosure in accordance with the provisions of 10 CFR 2.390. A redacted version of Enclosure 1 is provided in Enclosure 2.
Please contact Lynne Gunderson, Licensing Engineer, at 651-267-7421, if additional information or clarification is required.
Summary of Commitments This letter makes no new commitments and no .revisions to existing commitments.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on May 9, 2016.
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Scott Northard .
Acting Site Vice President, Prairie Island Nuclear Generating Plant Northern States Power Company - Minnesota Enclosures (2) cc: Administrator, Region Ill, USNRC Project Manager, Prairie Island Nuclear Generating Plant, USNRC Resident Inspector, Prairie Island Nuclear Generating Plant, USNRC