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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
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:Technical Specifications
MONTHYEARML22357A1002023-03-31031 March 2023 and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Issuance of Amendments Standard Emergency Plan and Consolidated Emergency Operations Facility ML22181A0002022-08-17017 August 2022 Issuance of Amendments Reactor Trip System Power Range Instrumentation Channels L-PI-22-003, Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2022-06-0707 June 2022 Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections ML22061A2062022-04-0101 April 2022 Issuance of Amendments TSTF-471, Rev. 1, TSTF-571-T, and Administrative Changes to Technical Specification Section 5.0 L-PI-21-029, Exigent License Amendment Request to Revise Technical Specification 3.7.8 to Allow a One-Time Extension of the Completion Time of Required Action B.12021-10-0707 October 2021 Exigent License Amendment Request to Revise Technical Specification 3.7.8 to Allow a One-Time Extension of the Completion Time of Required Action B.1 ML20346A0202021-03-15015 March 2021 Issuance of Amendment Nos. 235 and 223, Adoption of Technical Specifications Task Force Traveler TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML20356A0022021-02-0505 February 2021 Issuance of Amendment Nos. 234 and 222, Revise Technical Specifications 3.2.1 and 5.6.5 Identified in Westinghouse Nuclear Safety Advisory Letters NSAL-09-05, Revision 1, and NSAL-15-1 ML20210M0142020-09-0808 September 2020 and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Issuance of Amendment Nos. 204, 231, and 219 TSTF-529 Clarify Use and Application Rules L-PI-20-001, License Amendment Request to Address Issues Identified in Westinghouse Nuclear Safety Advisory Letter NSAL-09-5, Revision 1, and NSAL-15-12020-01-29029 January 2020 License Amendment Request to Address Issues Identified in Westinghouse Nuclear Safety Advisory Letter NSAL-09-5, Revision 1, and NSAL-15-1 L-PI-19-041, Application to Revise Technical Specifications to Adopt TSTF-547, Clarification of Rod Position Requirements2019-12-23023 December 2019 Application to Revise Technical Specifications to Adopt TSTF-547, Clarification of Rod Position Requirements L-PI-19-040, License Amendment Request: Revise Technical Specification 5.5.14 to Permanently Extend Containment Leakage Rate Test Frequency2019-10-0707 October 2019 License Amendment Request: Revise Technical Specification 5.5.14 to Permanently Extend Containment Leakage Rate Test Frequency ML19045A4802019-04-16016 April 2019 Issuance of Amendment Nos. 226 and 214 Adoption of TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control - RITSTF Initiative 5B ML19029A0942019-01-29029 January 2019 Issuance of Amendment No. 213, One-Time Technical Specification Change to Extend Completion Time for EDGs D5 and D6 (Emergency Circumstances) ML17362A2022018-03-0505 March 2018 Issuance of Amendment Concerning Revision to the Prairie Island Nuclear Generating Plant, Units 1 and 2 Emergency Plan (CAC Nos. MF9345 and MF9346; EPID L-2017-LLA-0175) ML16133A4062016-06-16016 June 2016 Issuance of Amendment Nos. 217 and 205, Adoption of Technical Specifications Task Force TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation (CAC Nos. MF6449 and MF6450) ML15264A2092015-11-30030 November 2015 Issuance of Amendment Nos. 216 and 204 Regarding Revisions to Technical Specification 3.3.3 and Renewed Facility Operating License ML15229A1762015-08-26026 August 2015 Issuance of Amendment Nos. 215 and 203 Regarding Revision to Licensing Basis Analysis for a Waste Gas Decay Tank Rupture ML15209A5122015-07-17017 July 2015 Technical Specifications - Updating Instructions -Effective Date: 7/24/2015 ML15209A5092015-07-17017 July 2015 Technical Specifications - Updating Instructions L-PI-15-030, Application to Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process2015-06-29029 June 2015 Application to Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process ML15086A0462015-05-21021 May 2015 Issuance of Amendment Nos. 214 and 202 Regarding Revisions to Technical Specification 3.8.1, AC Sources - Operating ML15062A0132015-05-20020 May 2015 Issuance of Amendments 213 and 201 to Revise TS 3.5.3, ECCS - Shutdown L-PI-15-004, Supplement to License Amendment Request (LAR) to Revise Technical Specification (TS) 3.5.3, ECCS (Emergency Core Cooling System)- Shutdown2015-02-26026 February 2015 Supplement to License Amendment Request (LAR) to Revise Technical Specification (TS) 3.5.3, ECCS (Emergency Core Cooling System)- Shutdown L-PI-14-034, License Amendment Request (LAR) to Revise Technical Specification (TS) 3.3.3, Event Monitoring (EM) Instrumentation, and Additional Conditions Related to Alternative Source Term License Amendment Implementation2014-12-11011 December 2014 License Amendment Request (LAR) to Revise Technical Specification (TS) 3.3.3, Event Monitoring (EM) Instrumentation, and Additional Conditions Related to Alternative Source Term License Amendment Implementation ML14058A2072014-02-19019 February 2014 Technical Specifications (3801 TS Markup) ML13214A0292013-08-0202 August 2013 Correction Letter for License Amendment Nos. 207 (Unit 1) and 194 (Unit 2) ML13113A4002013-07-0202 July 2013 License Amendments TSTF-510 L-PI-13-030, License Amendment Request (LAR) to Add a Methodology to Technical Specification (TS) 5.6.5, Core Operating Limits Report (Colr).2013-05-23023 May 2013 License Amendment Request (LAR) to Add a Methodology to Technical Specification (TS) 5.6.5, Core Operating Limits Report (Colr). ML13093A3442013-05-0909 May 2013 License Amendments for Fuel Oil System and TSTF-501 L-PI-12-028, License Amendment Request (LAR) to Revise Technical Specification (TS) 3.8.1, AC Sources - Operating Emergency Diesel Generator Voltage Limits2012-05-15015 May 2012 License Amendment Request (LAR) to Revise Technical Specification (TS) 3.8.1, AC Sources - Operating Emergency Diesel Generator Voltage Limits L-PI-12-013, Response to Requests for Additional Information Associated with Adoption of the Alternative Source Term (AST) Methodology2012-02-24024 February 2012 Response to Requests for Additional Information Associated with Adoption of the Alternative Source Term (AST) Methodology ML1129011152011-12-0101 December 2011 Issuance of Amendments Revision of Technical Specifications 5.2.1, Onsite and Offsite Organizations and TS 5.3, Plant Staff Qualifications. L-PI-11-037, License Amendment Request to Add Diesel Fuel Oil License Bases and Revise Technical Specifications 3.7.8 Re Cooling Water System & 3.8.3 Re Diesel Fuel Oil2011-08-11011 August 2011 License Amendment Request to Add Diesel Fuel Oil License Bases and Revise Technical Specifications 3.7.8 Re Cooling Water System & 3.8.3 Re Diesel Fuel Oil ML11172A0222011-06-27027 June 2011 Technical Specifications, Unit 2, Renewed Facility Operating License for Prairie Island Nuclear Generating Plant ML11172A0202011-06-27027 June 2011 Technical Specifications, Unit 1, Renewed Facility Operating License for Prairie Island Nuclear Generating Plant L-PI-11-016, License Amendment Request (LAR) to Revise Surveillance Requirement (SR) Footnote in Technical Specification (TS) 3.8.1, AC Sources - Operating.2011-02-0303 February 2011 License Amendment Request (LAR) to Revise Surveillance Requirement (SR) Footnote in Technical Specification (TS) 3.8.1, AC Sources - Operating. L-PI-10-104, Supplement to Exigent License Amendment Request to Modify Technical Specifications Surveillance Requirement 3.8.1.102010-10-20020 October 2010 Supplement to Exigent License Amendment Request to Modify Technical Specifications Surveillance Requirement 3.8.1.10 ML1025715492010-09-16016 September 2010 Correction to Amendment Nos. 195 and 184 Regarding Technical Specification Changes to Control Room Habitability Requirements ML0925703672009-09-15015 September 2009 Correction to Technical Specifications (TAC Nos. MD9142 and MD9143) L-PI-08-080, License Amendment Request (LAR) to Revise Emergency Diesel Generator (EDG) Test Loads in Surveillance Requirement (SR) 3.8.1.3 and SR 3.8.1.92008-11-0404 November 2008 License Amendment Request (LAR) to Revise Emergency Diesel Generator (EDG) Test Loads in Surveillance Requirement (SR) 3.8.1.3 and SR 3.8.1.9 ML0826815912008-09-22022 September 2008 (PINGP-1 and 2), Technical Specifications ISFSI, Issuance of Amendments to Conform the Facility Operating Licenses to Reflect Transfer of Operating Authority (TAC L24245) ML0826812912008-09-22022 September 2008 Revised Operating Licenses & Technical Specifications, Issuance of Amendments to Conform the Facility Operating Licenses to Reflect Transfer of Operating Authority (TAC L24245, MD9622 and MD9623) ML0820504452008-07-18018 July 2008 Tech Spec Pages for Amendments 186 & 176 Adopting Provisions of Regulatory Guide (Rg) 1.52 Revision 3 ML0818402342008-06-27027 June 2008 Prairie, Units 1 and 2, Tech Spec Pages for Amendments 185 and 175 Regarding Incorporation of TS Task Force Travelers TSTF-479, TSTF-485 and TSTF-497 ML0812705062008-05-0101 May 2008 Submittal of Entire Re-Issue of ISFSI Technical Specifications ML0801404252008-01-28028 January 2008 Issuance of Amendments (TAC Nos. MD4209 & MD4210) - Tech Specs ML0735204002007-12-14014 December 2007 Technical Specifications in Support of Containment Sump Resolution L-PI-07-086, License Amendment Request (LAR) to Revise Containment Spray Nozzle Surveillance Requirements (SR)2007-11-19019 November 2007 License Amendment Request (LAR) to Revise Containment Spray Nozzle Surveillance Requirements (SR) ML0728403542007-10-31031 October 2007 Tech Spec Page for Amendments 181 and 171, Revise TS 3.7.2 Main Steam Valves Closure Times by Relocating the Isolation Valve Closure Times to a Licensee-Controlled Document Identified as a Bases Reference L-PI-07-061, License Amendment Request (LAR) to Increase the Unit 1 Emergency Diesel Generators' (EDG) Monthly Test Load2007-08-16016 August 2007 License Amendment Request (LAR) to Increase the Unit 1 Emergency Diesel Generators' (EDG) Monthly Test Load 2023-03-31
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 September 15, 2009 Mr. Mark A. Schimmel Site Vice President - Acting Prairie Island Nuclear Generating Plant Northern States Power - Minnesota 1717 Wakonade Drive East Welch, MN 55089 SUB..IECT: PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 CORRECTION TO TECHNICAL SPECIFICATIONS (TAC NOS. MD9142 AND MD9143)
Dear Mr. Schimmel:
On July 1, 2009 (Agencywide Documents Access and Management System Accession No. ML091460809), the U.S. Nuclear Regulatory Commission (NRC) issued Amendment No. 192 to Facility Operating License No. DPR-42 and Amendment No. 181 to Facility Operating License No. DPR-60 for the Prairie Island Nuclear Generating Plant, Units 1 and 2 (PINGP),
respectively. The amendments consisted of changes to the facility operating licenses and the Technical Specifications (TSs) in response to your application dated June 26,2008, as supplemented by letters dated August 4, August 26, and November 14, 2008, and January 30, February 9, February 20, March 12, and May 4 (2 letters) 2009.
The amendments revised the PINGP TSs to allow the use of Westinghouse 422 VANTAGE+
nuclear fuel and made changes to certain references identified in the Design Features section of the TSs.
TS page 2.0-1, issued with the amendments, contained two editorial errors. In TS section 2.1.1.1, the phrase "... for OFA fuel" was inadvertently retained in the issued TS page. The marked-up TS page submitted with the June 26, 2008, application, correctly showed the change to remove these words from the sentence. Also, in TS Section 2.1.1.2 (b), the abbreviation for weight percent (w/o) was erroneously notated in subscript font.
TS page 2.0-1 has been revised to correct the editorial errors that were inadvertently introduced when the NRC processed Amendment Nos. 192 and 181. Please replace the corresponding page from the TS with the corrected page 2.0-1 enclosed with this letter.
M. Schimmel -2 This correction does not change any of the conclusions in the safety evaluation associated with these amendments. Please contact me at (301) 415-4037 if you have any questions on this issue.
Sincerely, Thomas J. Wengert, Senior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-282 and 50-306
Enclosure:
Corrected TS Page 2.0-1 cc w/encls: Distribution via ListServ
SLs 2.0 2.0 SAFETY LIMITS (SLs) 2.1 SLs 2.1.1 Reactor Core SLs In MODES 1 and 2, the combination of THERMAL POWER, Reactor Coolant System (RCS) highest loop average temperature, and pressurizer pressure shall not exceed the limits specified in the COLR and the following SLs shall not be exceeded:
2.1.1.1 The departure from nucleate boiling ratio (DNBR) shall be maintained> 1.17 for WRB-1 DNB correlation.
2.1.1.2 The peak fuel centerline temperature shall be maintained as follows:
a) <5080 of, decreasing by 58 OF per 10,000 MWDIMTU bUffiup, for fuel containing U02; b) <<5080 OF minus 6.75 OF per wlo Gdz0 3 ), decreasing by 58 OF per 10,000 MWDIMTU bUffiup, for fuel containing gadolinia; 2.1.2 RCS Pressure SL In MODES 1, 2, 3, 4, and 5, the RCS pressure shall be maintained
- s 2735 psig.
2.2 SL Violations 2.2.1 If SL 2.1.1 is violated, restore compliance and be in MODE 3 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
2.2.2 If SL 2.1.2 is violated:
2.2.2.1 In MODE 1 or 2, restore compliance and be in MODE 3 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
2.2.2.2 In MODE 3, 4, or 5, restore compliance within 5 minutes.
Prairie Island Unit 1 - Amendment No. ~ ~ 192 Units land 2 2.0-1 Unit 2 - Amendment No. -l-49 BJ. 181 Revised hy letter dated Septe~her 15, 200Q
M. Schimmel -2 This correction does not change any of the conclusions in the safety evaluation associated with these amendments. Please contact me at (301) 415-4037 if you have any questions on this issue.
Sincerely, IRA by M. Chawla fori Thomas J. Wengert, Senior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-282 and 50-306
Enclosure:
Corrected TS Page 2.0-1 cc w/encls: Distribution via ListServ DISTRIBUTION PUBLIC LPL3-1 rlf RidsNrrDorlLpl3-1 Resource RidsOgcRp Resource RidsNrrPMPrairielsland Resource RidsNrrLABTully Resource RidsNrrDirsltsb Resource RidsAcrsAcnw_MailCTR Resource RidsRgn3MailCenter Resource RidsNrrDorlDpr Resource ADAMS Accession No ML092570367 OFFICE NRRlLPL3-11 PM NRRlLPL3-11 LA NRRlLPL3-1/(A)BC NAME TWengert BTuily TWengert (M. Chawla for) (T. Harris for)
DATE 09/15/09 09/15/09 09/15/09 OFFICIAL RECORD COpy