Letter Sequence RAI |
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MONTHYEARL-PI-08-047, License Amendment Request for Technical Specifications Changes to Allow Use of Westinghouse 0.422-inch OD 14x14 Vantage+ Fuel2008-06-26026 June 2008 License Amendment Request for Technical Specifications Changes to Allow Use of Westinghouse 0.422-inch OD 14x14 Vantage+ Fuel Project stage: Request ML0822101322008-07-22022 July 2008 Email - Prairie Island Acceptance Review Questions for LAR to Allow Use of West. 14X14 Vantage+ Fuel (TACs MD9142/MD9143) Project stage: Acceptance Review ML0820605722008-07-28028 July 2008 Request for Supplemental Information, Acceptance Review of License Amendment Request Project stage: Acceptance Review L-PI-08-071, Supplement to License Amendment Request for Technical Specifications Changes to Allow Use of Westinghouse 0.422-Inch OD 14x14 Vantage+ Fuel2008-08-26026 August 2008 Supplement to License Amendment Request for Technical Specifications Changes to Allow Use of Westinghouse 0.422-Inch OD 14x14 Vantage+ Fuel Project stage: Supplement ML0822614492008-08-28028 August 2008 Acceptance of Requested Licensing Action Technical Specification Changes to Allow Use of Westinghouse 0.422-inch OD 14X14 Vantage+ Fuel Project stage: Acceptance Review ML0828106452008-10-17017 October 2008 Request for Additional Information Related to License Amendment Request for Technical Specifications Changes to Allow Use of Westinghouse 0.422-Inch OD 14X14 Vantage+Fuel (Tac No. MD9142, MD9143) Project stage: RAI L-PI-08-096, Response to Request for Additional Information Regarding License Amendment Request for Technical Specifications Changes to Allow Use of Westinghouse. 0.422- Inch OD 14x14 Vantage + Fuel2008-11-14014 November 2008 Response to Request for Additional Information Regarding License Amendment Request for Technical Specifications Changes to Allow Use of Westinghouse. 0.422- Inch OD 14x14 Vantage + Fuel Project stage: Response to RAI ML0833002102008-12-15015 December 2008 Request for Additional Information Related to License Amendment Request for Technical Specifications Changes to Allow Use of Westinghouse 0.422-Inch OD 14X14 Vantage + Fuel (TAC Nos. MD9142/9143) Project stage: RAI ML0835200472008-12-30030 December 2008 Request Withholding Information from Public Disclosure for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Tac Nos. MD9142 and MD9143) Project stage: Other ML0835800982009-01-12012 January 2009 Request for Additional Information Related to License Amendment Request for Technical Specifications Changes to Allow Use of Westinghouse 0.422-Inch OD 14X14 Vantage + Fuel (TAC Nos. MD9142/9143) Project stage: RAI L-PI-09-011, Response to Request for Additional Information Regarding License Amendment Request for Technical Specifications Changes to Allow Use of Westinghouse 0.422-Inch OD 14x14 Vantage+ Fuel2009-01-30030 January 2009 Response to Request for Additional Information Regarding License Amendment Request for Technical Specifications Changes to Allow Use of Westinghouse 0.422-Inch OD 14x14 Vantage+ Fuel Project stage: Response to RAI L-PI-09-022, Response to Request for Additional Information Regarding License Amendment Request for Technical Specifications Changes to Allow Use of Westinghouse 0.422-Inch OD 14x14 Vantage+ Fuel2009-02-0909 February 2009 Response to Request for Additional Information Regarding License Amendment Request for Technical Specifications Changes to Allow Use of Westinghouse 0.422-Inch OD 14x14 Vantage+ Fuel Project stage: Response to RAI ML0901403342009-02-11011 February 2009 RAI for TS Changes to Allow Use of Westinghouse 0.422-inch OD 14x14 Vantage+Fuel Project stage: RAI L-PI-09-025, Response to Request for Additional Information Regarding License Amendment Request for Technical Specifications Changes to Allow Use of Westinghouse 0.422-Inch 14x14 Vantage+ Fuel2009-02-20020 February 2009 Response to Request for Additional Information Regarding License Amendment Request for Technical Specifications Changes to Allow Use of Westinghouse 0.422-Inch 14x14 Vantage+ Fuel Project stage: Response to RAI L-PI-09-034, Response to Request for Additional Information Regarding License Amendment Request for Technical Specifications Changes to Allow Use of Westinghouse 0.422-Inch 14x14 Vantage + Fuel2009-03-12012 March 2009 Response to Request for Additional Information Regarding License Amendment Request for Technical Specifications Changes to Allow Use of Westinghouse 0.422-Inch 14x14 Vantage + Fuel Project stage: Response to RAI ML0907210882009-03-12012 March 2009 Enclosure 1, Non-Proprietary Responses to Requests for Additional Information License Amendment Request for Technical Specifications Changes to Allow Use of Westinghouse 422V+ Fuel Project stage: Response to RAI ML0907102152009-03-25025 March 2009 Request for Withholding Information from Public Disclosure for Prairie Island Nuclear Generating Plant, Units 1 and 2 Project stage: Withholding Request Acceptance L-PI-09-066, 422V+Fuel Transition Project RAI Response-EMCB RAI-1(a)2009-04-27027 April 2009 422V+Fuel Transition Project RAI Response-EMCB RAI-1(a) Project stage: Other L-PI-09-065, Supplemental Information Regarding License Amendment Request for Technical Specifications Changes to Allow Use of Westinghouse 0.422-Inch OD 14x14 Vantage+Fuel2009-05-0404 May 2009 Supplemental Information Regarding License Amendment Request for Technical Specifications Changes to Allow Use of Westinghouse 0.422-Inch OD 14x14 Vantage+Fuel Project stage: Supplement ML0913103842009-05-0404 May 2009 Clarification of Response to Request for Additional Information Regarding License Amendment Request for Technical Specifications Changes to Allow Use of Westinghouse 0.422-Inch 14x14 Vantage+ Fuel Project stage: Response to RAI ML0914905612009-06-0808 June 2009 Request for Withholding Information from Public Disclosure for Prairie Island Nuclear Generating Plant, Units 1 and 2 Project stage: Withholding Request Acceptance ML0917402012009-06-25025 June 2009 Public Letter Draft Safety Evaluation for License Amendment Request for Technical Specifications Changes to Allow Use of Westinghouse 0.422-inch OD 14x14 Vantage+ Fuel Project stage: Draft Approval ML0914608092009-07-0101 July 2009 Issuance of Amendments Technical Specifications Changes to Allow Use of Westinghouse 0.422-Inch OD 14X14 Vantage + Fuel Project stage: Approval ML0922403322009-08-31031 August 2009 Correction to Safety Evaluation Supporting Amendment Nos. 192 and 181 Technical Specification Changes to Allow Use of Westinghouse 0.422-Inch OD 14 X 14 Vantage+ Fuel (TAC Nos. MD9142/MD9143) Project stage: Approval ML0925703672009-09-15015 September 2009 Correction to Technical Specifications (TAC Nos. MD9142 and MD9143) Project stage: Other 2009-02-11
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Category:Letter
MONTHYEARML24298A0552024-10-30030 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 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 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 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 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 ML24089A2382024-04-29029 April 2024 Summary of Nuclear Property Insurance 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 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) 2024-09-27
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24197A2012024-07-15015 July 2024 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000282/2024004 ML24149A3712024-05-29029 May 2024 (Ping) - Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection ML24141A0452024-05-20020 May 2024 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection ML24116A2532024-04-25025 April 2024 Final Request for Additional Information for LAR to Revise SR 3.8.1.2 Note 3 (EPID: L- 2023-LLA-0135) ML24045A0862024-02-12012 February 2024 Final RAI for Alternative RR-09 ML23335A1152023-12-0101 December 2023 NRR E-mail Capture - Prairie Island Units 1 and 2 - Request for Additional Information LAR to Revise TS 3.7.8 Required Actions ML23248A3462023-09-0505 September 2023 NRR E-mail Capture - Request for Additional Information for Monticello Nuclear Generating Plant and Prairie Island Nuclear Generating Plant - Decommissioning Funding Status Reports ML23214A2032023-08-0202 August 2023 Request for Information for an NRC Quadrennial Comprehensive Engineering Team Inspection: Inspection Report 05000282/2024010; 05000306/2024010 ML23199A0922023-07-18018 July 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000306/2023004 ML23096A3082023-04-0707 April 2023 Notification of Inspection an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information ML23055B0562023-02-27027 February 2023 Request for Information for NRC Commercial Grade Dedication Inspection Inspection Report 05000282/2023010 and 05000306/2023010 ML23053A1432023-02-22022 February 2023 Information Request to Support Upcoming Problem Identification and Resolution (Pi&R) Inspection at Prairie Island Nuclear Generating Plant ML22166A4112022-06-15015 June 2022 NRR E-mail Capture - Request for Additional Information Prairie Island Nuclear Generating Plant, Unit 2, Alternative RR-08, PIV Leakage ML22160A6022022-06-0909 June 2022 NRR E-mail Capture - Draft Request for Additional Information Prairie Island Nuclear Generating Plant, Units 1 and 2, 24-Month Operating Cycle Amendment ML22145A4152022-05-25025 May 2022 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000282/2022402 05000306/2022402 ML22131A2652022-05-11011 May 2022 NRR E-mail Capture - Request for Additional Information Xcel Energy Amendment Request to Create a Common Eplan and EOF for Monticello and Prairie Island ML22130A5792022-05-11011 May 2022 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection ML21321A0452021-11-10010 November 2021 Request for Additional Information: Prairie Island 24-Month Cycle Amendment Request ML21305A0102021-10-29029 October 2021 NRR E-mail Capture - Request for Additional Information Prairie Island Cooling Water Amendment ML21252A0122021-08-30030 August 2021 NRR E-mail Capture - Request for Additional Information Amendment Request to Adopt TSTF-471 and 517-T for Prairie Island ML21147A5232021-06-0303 June 2021 Prarie Island Nuclear Generating Plant, Units 1 and 2 - Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection ML21131A0752021-05-10010 May 2021 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000282/2021004; 05000306/2021004 ML21099A0972021-04-0909 April 2021 Information Request to Support Upcoming Temporary Instruction 2515/194 Inspection; Inspection Report 05000282/2021012 and 05000306/2021012 ML21062A0532021-03-0202 March 2021 Information Request to Support Upcomng Problem Identification and Resolution (Pi&R) Inspection at the Prairie Island Nuclear Generating Plant ML21033A6112021-02-0101 February 2021 Request for Information for an NRC Triennial Baseline Design Bases Assurance Inspection (Team); Inspection Report 05000282/2021010 and 05000306/2021010 ML20343A1292020-12-0808 December 2020 NRR E-mail Capture - Request for Additional Information ML20192A1442020-07-0707 July 2020 NRR E-mail Capture - Request for Additional Information Prairie Island License Amendment Request to Adopt TSTF-505 ML20189A1782020-07-0606 July 2020 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000282/2020004; 05000306/2020004 ML20133K0692020-05-14014 May 2020 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection ML20077K6242020-04-13013 April 2020 License Amendment Request - Request for Additional Information ML20052F4102020-02-21021 February 2020 Notification of Nrc Design Bases Assurance Inspection (Programs) (05000282/202010; 05000306/202010) and Initial Request for Information ML20035F1552020-02-0404 February 2020 NRR E-mail Capture - Request for Additional Information Monticello and Prairie Island Alternative Requests to Adopt Code Cases N-786-3 and N-789-3 (Epids: L-2019-LLR-0078 and L-2019-LLR-0079) ML19233A0032019-08-14014 August 2019 NRR E-mail Capture - Request for Additional Information Prairie Island Relief Requests 1-RR-10 and 2-RR-10 ML19057A1652019-02-26026 February 2019 NRR E-mail Capture - Request for Additional Information Prairie Island 50.69 Amendment Request ML18313A0832018-11-0707 November 2018 NRR E-mail Capture - Request for Additional Information Prairie Island NFPA-805 License Condition Modification Amendment Request ML18264A1912018-09-19019 September 2018 NRC Information Request (9/19/2018); Part B Items (Onsite) IP 71111.08 - E-Mailed 09/19/18 (DRS-M.Holmberg) ML18235A2982018-08-23023 August 2018 NRR E-mail Capture - Request for Additional Information Prairie Island TSTF-425 License Amendment Request ML18169A4202018-06-25025 June 2018 Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment to Modify Renewed Facility Operating License Paragraph 2.C(4)(c) ML18025C0152018-01-24024 January 2018 Request for Information for an NRC Triennial Baseline Design Bases Assurance Inspection (Team): Inspection Report 05000282/2018011; 05000306/2018011 (DRS-A.Dunlop) ML17277B3332017-10-0404 October 2017 NRR E-mail Capture - Request for Additional Information Prairie Island Special Heavy Lifting Devices LAR ML17249A9232017-09-0606 September 2017 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000282/2017004; 05000306/2017004 (Exf) ML17235A9982017-08-23023 August 2017 NRR E-mail Capture - Request for Additional Information Prairie Island EAL Scheme Change ML17221A3892017-08-0909 August 2017 NRR E-mail Capture - Request for Additional Information for Prairie Island Nuclear Generating Plant License Amendment Request Dated February 23, 2017 Emergency Response Organization ML17219A0762017-08-0707 August 2017 NRR E-mail Capture - Request for Additional Information for Prairie Island Nuclear Generating Plant License Amendment Request Dated February 23, 2017 Emergency Response Organization ML17038A5132017-02-0707 February 2017 NRR E-mail Capture - Prairie Island NFPA 805 LAR, PRA RAI 21.01 ML17018A4272017-01-18018 January 2017 NRR E-mail Capture - Request for Additional Information: Prairie Island License Amendment Request to Revise Technical Specification 3.8.7 to Remove Non-Conservative Required Action ML16326A3532016-11-18018 November 2016 NRR E-mail Capture - Draft Request for Information Related to Prairie Island NFPA-805 License Amendment ML16265A1652016-09-20020 September 2016 Notification of an NRC Triennial Heat Sink Performance Inspection and Request for Information; Inspection Report 05000282/2016004; 05000306/2016004 (Gfo) ML16189A2052016-07-0707 July 2016 Notification of NRC Inspection and Request for Information ML16113A1612016-04-21021 April 2016 Information Request to Support Upcoming Problem Identification and Resolution (Pi&R) Inspection at Prairie Island Nuclear Generating Plant, Units 1 and 2 2024-07-15
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 January 12, 2009 Mr. Michael D. Wadley Site Vice President Prairie Island Nuclear Generating Plant Northern States Power Company - Minnesota 1717 Wakonade Drive East Welch, MN 55089
SUBJECT:
PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 REQUEST FOR ADDITIONAL INFORMATION RELATED TO LICENSE AMENDMENT REQUEST FOR TECHNICAL SPECIFICATIONS CHANGES TO ALLOW USE OF WESTINGHOUSE 0.422-INCH 00 14X14 VANTAGE+ FUEL (TAC NOS. MD9142 AND MD9143)
Dear Mr. Wadley:
By letter to the U.S. Nuclear Regulatory Commission (NRC) dated June 26, 2008, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML081820137), as supplemented by letters dated August 4, (ADAMS Accession No. ML082210260), August 26, (ADAMS Accession No. ML082400518), and November 14, 2008, (ADAMS Accession No. ML083190820), Nuclear Management Company, LLC, a predecessor license holder to the Northern States Power Company, a Minnesota Corporation, submitted a request for Technical Specification changes to allow the use of Westinghouse 0.422-inch outside diameter 14X14 VANTAGE+ fuel for Prairie Island Nuclear Generating Plant, Units 1 and 2.
The NRC staff is reviewing your submittal and has determined that additional information is required to complete the review. The specific information requested is addressed in the enclosure to this letter. During a discussion with your staff on December 19, 2008, it was agreed that you would provide a response within 30 days of this letter.
The NRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for staff review and contribute toward the NRC's goal of efficient and effective use of staff resources. If circumstances result in the need to revise the requested response date, please contact me at (301) 415-4037.
Sincerely, Thomas J. Wengert, Senior Pro' Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-282 and 50-306
Enclosure:
Request for Additional Information cc w/encl: Distribution via ListServ
REQUEST FOR ADDITIONAL INFORMATION PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 DOCKET NOS. 50-282 AND 50-306 In reviewing the Nuclear Management Company, LLC', submittal dated June 26, 2008 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML081821037), as supplemented by letters dated August 4 (ADAMS Accession No. ML082210260), August 26 (ADAMS Accession No. ML082400518), and November 14, 2008 (ADAMS Accession No. ML083190820), which requested technical specification changes related to a change in fuel type from Westinghouse OAOO-inch outside diameter (OD) Vantage+
(400V+) fuel to Westinghouse OA22-inch OD Vantage+ (422V+) fuel for Prairie Island Nuclear Generating Plant, Units 1 and 2 (PINGP), the U.S. Nuclear Regulatory Commission (NRC) staff has determined that further clarification of the November 14, 2008, request for additional information (RAI) response is needed in order to complete its review. The same RAI numbering used in the November 14, 2008, RAI response is referenced for tracking purposes.
- 2. The Revised Thermal Design Procedure (RTDP) combines uncertainties in a way that is somewhat different from the way proposed in this license amendment request, which reduces the assumed uncertainty and recovers it by assuming a bounding power level. Please show this treatment is acceptably conservative by providing comparative data. Compare the Design Limit departure from nucleate boiling ratio (DNBR) for PINGP using the traditional RTDP to that obtained using the bounding power level assumption with a reduced uncertainty. Also, compare the DNBR results for the limiting DNBR transient using the RTDP analytic process and using the bounding power level assumption with a reduced uncertainty.
5b. The licensing report did not seem to indicate clearly that two separate transients had been analyzed. The NRC staff requests NSPM to distinguish between the two.
- 6. The NRC staff requests NSPM to provide additional information concerning the core flow rates, the injection source assumed to be providing the diluting flow, and the total reactor coolant system (RCS) volume to justify the use of total RCS volume as a figure of merit, as opposed to the core coolant volume, as requested by the staff. Noting that the RCS configuration may change depending on the Operating Mode, the staff requests NSPM to consider all modes for the potential for an impact on the boron dilution analysis when preparing its response.
- On September 22, 2008, Nuclear Management Company, LLC (NMC), transferred its operating authority to Northern States Power Company, a Minnesota Corporation (NSPM). By letter dated September 3, 2008, NSPM stated that it would assume responsibility for actions and commitments submitted by NMC.
ENCLOSURE
Mr. Michael D. Wadley Site Vice President Prairie Island Nuclear Generating Plant Northern States Power Company - Minnesota 1717 Wakonade Drive East Welch, MN 55089
SUBJECT:
PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 REQUEST FOR ADDITIONAL INFORMATION RELATED TO LICENSE AMENDMENT REQUEST FOR TECHNICAL SPECIFICATIONS CHANGES TO ALLOW USE OF WESTINGHOUSE 0.422-INCH 00 14X14 VANTAGE+ FUEL (TAC NOS. MD9142 AND MD9143)
Dear Mr. Wadley:
By letter to the U.S. Nuclear Regulatory Commission (NRC) dated June 26, 2008, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML081820137), as supplemented by letters dated August 4, (ADAMS Accession No. ML082210260), August 26, (ADAMS Accession No. ML082400518), and November 14, 2008, (ADAMS Accession No. ML083190820), Nuclear Management Company, LLC, a predecessor license holder to the Northern States Power Company, a Minnesota Corporation, submitted a request for Technical Specification changes to allow the use of Westinghouse 0.422-inch outside diameter 14X14 VANTAGE+ fuel for Prairie Island Nuclear Generating Plant, Units 1 and 2.
The NRC staff is reviewing your submittal and has determined that additional information is required to complete the review. The specific information requested is addressed in the enclosure to this letter. During a discussion with your staff on December 19, 2008, it was agreed that you would provide a response within 30 days of this letter.
The NRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for staff review and contribute toward the NRC's goal of efficient and effective use of staff resources. If circumstances result in the need to revise the requested response date, please contact me at (301) 415-4037.
Sincerely, IRAJ Thomas J. Wengert, Senior Project Manager.
Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-282 and 50-306
Enclosure:
Request for Additional Information cc w/encl: Distribution via ListServ DISTRIBUTION:
PUBLIC LPL3-1 RIF RidsNrrDorlLpl3-1 Resource RidsNRRPMTWengert Resource RidsNrrLATHarris Resource RidsNrrDssSrxb Resource RidsAcrsAcnw_MailCTR Resource RidsOgcRp Resource B. Parks, NRR RidsRgn3MailCenter Resource RidsNrrDorlDpr Resource ADAMS Accession Number: ML083580098 OFFICE LPL3-1/PM LPL3-1/LA NRR/DSS/SRXB/BC LPL3-1/BC NAME TWengert THarris GCranston LJames DATE 01/02/09 01/02/09 01/07/09 01/12/09 OFFICIAL RECORD COpy