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MONTHYEAR0CAN091302, Assistance in Obtaining Information on Dams2013-09-30030 September 2013 Assistance in Obtaining Information on Dams Project stage: Request L-PI-14-024, 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(0 Regarding Recommendation 2.1, Flooding, of the Near-Term Task For2014-03-10010 March 2014 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(0 Regarding Recommendation 2.1, Flooding, of the Near-Term Task Force Project stage: Request L-14-113, Extension Request Regarding the Flood Hazard Reevaluation Report Required by NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendation 2.1 of the Near-Term Task Force (NTTF) Review of Insights.2014-03-11011 March 2014 Extension Request Regarding the Flood Hazard Reevaluation Report Required by NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendation 2.1 of the Near-Term Task Force (NTTF) Review of Insights. Project stage: Request 0CAN031401, Required Response 2 to March 12, 2012, Request for Information (Rfi), Enclosure 2, Recommendation 2.1, Flood Hazard Evaluation Report Arkansas Nuclear One - Units 1 and 22014-03-12012 March 2014 Required Response 2 to March 12, 2012, Request for Information (Rfi), Enclosure 2, Recommendation 2.1, Flood Hazard Evaluation Report Arkansas Nuclear One - Units 1 and 2 Project stage: Request 0CAN041402, Required Response 2 to March 12, 2012, Request for Information (Rfi), Enclosure 2, Recommendation 2.1, Flood Hazard Evaluation Report2014-04-14014 April 2014 Required Response 2 to March 12, 2012, Request for Information (Rfi), Enclosure 2, Recommendation 2.1, Flood Hazard Evaluation Report Project stage: Request ML14168A0182014-05-16016 May 2014 Xcel Energy Responses to NRC Questions Regarding Flood Hazard Reevaluation Report Extension Requests Project stage: Other ML14153A0242014-05-16016 May 2014 Xcel Energy'S Presentation Slides Supporting a May 16, 2014, Public Meeting to Discuss the Flood Hazard Reevaluation Schedule for the Monticello and Prairie Island Nuclear Generating Plants Project stage: Meeting ML14153A0252014-06-20020 June 2014 Meeting Summary - Public Meeting on May 16, 2014, to Discuss Xcel Energy'S Flood Hazard Reevaluation Extension Request for the Monticello and Prairie Island Nuclear Generating Plants Project stage: Meeting ML14162A3712014-06-26026 June 2014 5/22/2014 Summary of Meeting with Entergy Operations, Inc. to Discuss Flooding Hazard Reevaluation Extension Request for Arkansas Nuclear One, Units 1 and 2; Near-Term Task Force Recommendation 2.1 Project stage: Meeting ML14171A5292014-07-17017 July 2014 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 Project stage: Approval ML14171A1662014-07-29029 July 2014 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 Project stage: Approval ML15155A6312015-06-0808 June 2015 Nuclear Regulatory Commission Plan for the Audit of Duke Energy Carolinas, Llc'S Flood Hazard Reevaluation Report Submittal Relating to the Near-Term Task Force Recommendation 2.1 Flooding for Catawba Nuclear Station, Units 1 and 2 Project stage: Other 2014-05-16
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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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Mr. Kevin K. Davison Site Vice President UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 29, 2014 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-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)
Dear Mr. Davison:
By letter dated March 12, 2012, 1 the U.S. Nuclear Regulatory Commission (NRC) issued a request for information pursuant to Title 10 of the Code of Federal Regulations, Section 50.54(f) (henceforth referred to as the 50.54(f) letter). The NRC issued the request as a part of implementing lessons-learned from the accident at the Fukushima Dai-ichi nuclear power plant. Enclosure 2 to the 50.54(f) letter requested licensees to perform a reevaluation of all external flooding hazards using present-day guidance and methodologies.
By letter dated May 11, 2012, 2 the NRC issued a prioritization of due dates for responses from all sites. The flooding hazard reevaluation report (FHRR) was due on March 12, 2014, for Prairie Island Nuclear Generating Plant (PINGP), Units 1 and 2. By letter dated March 5, 2014, 3 Northern States Power Company, a Minnesota corporation (NSPM, the licensee) requested NRC assistance in obtaining the U.S. Army Corps of Engineers (USACE) analysis of dams that could impact the flood levels at the PINGP site. By letter dated March 10, 2014, 4 NSPM requested a delay in submittal of 10 months after receiving the USACE final analysis for PINGP, Units 1 and 2. The licensee's justification for this request is that the results of the USACE analysis are necessary to complete the flooding hazard reevaluation (FHR) and estimates about 10 months to incorporate the results and finalize the FHRR. 1 The 50.54(f) letter is available in the Agencywide Documents Access and Management System (ADAMS) under Accession No. ML12053A340.
2 The prioritization letter is available in ADAMS under Accession No. ML12097A509.
3 The request for assistance in obtaining USAGE analysis is available in ADAMS under Accession No. ML14064A291.
4 The extension request from NSPM is available in ADAMS under Accession No. ML14069A544.
K. Davison The NRC reviewed the justification provided by the licensee and considered the following factors when reviewing the new schedule:
- As stated in the NRC's interim staff guidance (ISG) JLD-ISG-2013-01, "Guidance for Assessment of Flooding Hazards Due to Dam Failure," dated July 29, 2013, 5 evaluating flooding hazards for nuclear power plants needs to include consideration of floods resulting from dam failures.
The FHR for the PINGP site needs to consider the six dams that are operated by USACE. The NRC entered into an interagency agreement with the USACE to provide the necessary information for NSPM to complete its FHR. Therefore, the FHR for PINGP, Units 1 and 2, cannot be completed until the NRC provides the analysis of the USACE dams to the licensee.
- As stated in the NRC's letter dated March 1, 2013, 6 "incomplete hazard reports that only contain an analysis of some flooding hazard mechanisms would not be of substantive benefit for staff review and would not be acceptable." Therefore, the licensee must incorporate the information requested from the USACE before a FHRR can be acceptable for submittal to the NRC in compliance with the request in the 50.54(f) letter.
- In the March 5, 2014, extension request NSPM provided a rationale for the extension.
This rationale was discussed in a public meeting on May 16, 2014.7 As noted-in the May 16, 2014, meeting summary NSPM provided additional information to support their request.8 The additional information included a discussion of task schedules, in which NSPM estimated 3 to 4 months for evaluation of the revised hydrology from the USACE information which NSPM estimates will take 3 to 4 months. Under the current USACE interagency agreement, those tasks that NSPM described in the additional information will be performed by the USACE and the licensee will not be responsible, nor be, required to perform these tasks.
- Based on discussions during the May 16, 2014, meeting and based on review of the information in the March 5, 2014, extension request and the supplemental information provided by NSPM the NRC staff concludes that NSPM has overestimated the time to integrate the USACE information.
Therefore, the integration of the USACE FHR with the licensee-developed FHR should not take 1 0 months if NSPM removes this duplicative task from the schedule.
5 JLD-ISG-2013-01 is available in ADAMS under Accession No. ML13151A153.
6 NRC's March 1, 2013, letter is available in ADAMS under Accession No. ML13044A561.
7 The May 16, 2014, meeting summary is available in ADAMS under Accession No. ML14153A025.
8 The supplemental information is documented in the May 16, 2014, summary and can also be found in ADAMS under Accession No. ML14168A018.
K. Davison
- The six month time frame to integrate the USACE FHR with the licensee developed FHR is consistent with the time frame requested by other licensees to perform a similar integration
- 9.
- The NRC staff further concludes that prior to receiving the USACE FHR information, NSPM can take steps now to ensure that once the USACE FHR is received it can be integrated with the licensee-developed FHR as expeditiously as possible.
The staff considers that NSPM's 1 0-month estimate be reduced by 4 months based on that designated portion of the analysis being performed by USACE, and that 6 months is a reasonable amount of time to integrate the USACE FHR with the licensee-developed analysis.
Given these considerations, the NRC staff considers the revised schedule proposed by NSPM to be unacceptable.
Accordingly, and based upon the authority granted to the Director, Office of Nuclear Reactor Regulation, the revised required response date for submitting the FHRR for PINGP, Units 1 and 2 is six months after NSPM receives the USACE final analysis.
NSPM is also requested to inform the staff by September 30, 2014, if the licensee-developed FHR (which is independent of the USACE analysis) results in a higher flood hazard relative to the design basis and if this is the case, what interim actions NSPM will take or plans to take to address the higher flood hazard. The NRC will include the date when the PINGP, Units 1 and 2 FHR is due, based on when the requested USACE information is transmitted to the licensee.
The transmittal letter will also note that if the USACE analysis results in a higher flood hazard relative to the design basis, the NRC staff will request that NSPM provide interim actions it will take or plans to take to address the higher flooding hazard within 60 days of receipt of the USACE analysis.
9 See Entergy's March 12, 2014 extension request for the Arkansas Nuclear One site available in ADAMS under Accession No. ML14071A459, and FirstEnergy Nuclear Operating Company's March 11, 2014, extension request for the Beaver Valley Power Station site available in ADAMS under Accession No. ML14070A371.
K. Davison If you have any questions regarding this matter, or if it is necessary to revise the submittal schedule, please contact your NRC project manager, Mr. Scott Wall, at (301) 415-2855 or via e-mail at Scott.Wall@nrc.gov.
Sincerely, Office of Nuclear Reactor Regulation Docket Nos. 50-282 and 50-306 cc: Listserv K. Davison If you have any questions regarding this matter, or if it is necessary to revise the submittal schedule, please contact your NRC project manager, Mr. Scott Wall, at (301) 415-2855 or via e-mail at Scott.Wall@nrc.gov.
Docket Nos. 50-282 and 50-306 cc: Listserv DISTRIBUTION:
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- 0. Sincerely, IRA by Jennifer Uhle for/ Daniel H. Dorman, Acting Director Office of Nuclear Reactor Regulation MMitchell, NRR DSkeen, JLD EMiller, DORL RTaylor, DSS RKuntz, JLD * . *1 **P v1a ema1 rev1ous1y concurre d OFFICE NRRJJLD/JHMB/PM NRR/JLD/JHMB/LA
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