Letter Sequence Other |
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TAC:MB0695, Ventilation System Envelope Allowed Outage Time (Approved, Closed) TAC:MB0696, Ventilation System Envelope Allowed Outage Time (Approved, Closed) |
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MONTHYEARML0135504172002-01-0808 January 2002 Request for Additional Information, Application for Conversion to Improved Technical Specifications, Section 3.7 Project stage: RAI ML0215400082002-06-0303 June 2002 Draft Safety Evaluation Conversion to Improved Technical Specifications Project stage: Draft Approval ML0215403012002-06-0303 June 2002 Draft of Safety Evaluation Project stage: Draft Approval ML0218300892002-07-15015 July 2002 Environmental Assessment and Finding No Significant Impact for the Proposed Conversion to the Improved TSs Project stage: Other ML0222100432002-07-26026 July 2002 Technical Specifications for License Amendment Nos. 158 and 149, Pages 1.1-1 to 3.4.13-1 (174 Pages) Project stage: Acceptance Review ML0220706582002-07-26026 July 2002 Individual Notice of Issuance, License Amendment Nos. 158 and 149, Conversion to Improved Technical Specifications Project stage: Other ML0221403592002-07-26026 July 2002 Technical Specification Bases for License Amendment Nos. 158 and 149, Pages B2.1.1-1 to B3.3.1-66 200 Pages) Project stage: Acceptance Review ML0221403702002-07-26026 July 2002 Technical Specification Bases for License Amendment Nos. 158 and 149, Pages B.3.3.2-1 to B3.4.13-13 (185 Pages) Project stage: Acceptance Review ML0221403942002-07-26026 July 2002 Technical Specification Bases for License Amendment Nos. 158 and 149, Pages B3.4.14-1 to B3.7.7-7 (186 Pages) Project stage: Other ML0221404122002-07-26026 July 2002 Technical Specification Bases for License Amendment Nos. 158 and 149, Pages B3.7.8-1 to B3.9.6-4 (194 Pages) Project stage: Acceptance Review ML0222100542002-07-26026 July 2002 Technical Specifications for License Amendment Nos. 158 and 149, Pages 3.4.13-1 to 5.0-4.5 (215 Pages) Project stage: Acceptance Review ML0230400542002-07-26026 July 2002 Attachment 2 to Safety Evaluation of Amendment No. 149 - Table a - Administrative Controls Project stage: Approval ML0230401182002-07-26026 July 2002 Attachment 4 to Safety Evaluation of Amendment No. 149 - Table L - Less Restrictive Changes Project stage: Approval ML0230401212002-07-26026 July 2002 Attachment 3 to Safety Evaluation of Amendment No. 149 - Table M - More Restrictive Changes Project stage: Approval ML0230401282002-07-26026 July 2002 Attachment 5 to Safety Evaluation of Amendment of 149 - Table Lr - Less Restrictive - Relocated Details Project stage: Approval ML0230401442002-07-26026 July 2002 Attachment 6 to Safety Evaluation of Amendment No. 149 - Table R - Relocated Specifications Project stage: Approval ML0230401512002-07-26026 July 2002 Attachment 7 to Safety Evaluation of Amendment No. 149 - Table U - Unused Numbers Project stage: Approval ML0220706542002-07-26026 July 2002 License Amendment Nos. 158 and 149, Conversion to Improved Technical Specifications (Safety Evaluation) Project stage: Approval ML0220706132002-07-26026 July 2002 License Amendment Nos. 158 and 149, Conversion to Improved Technical Specifications (Cover Letter, Amendment, License Pages) Project stage: Other 2002-06-03
[Table View] |
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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:License-Operating (New/Renewal/Amendments) DKT 50
MONTHYEARML23356A0032024-01-17017 January 2024 Issuance of Amendments Revise Technical Specification 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) ML23115A4072023-04-26026 April 2023 Correction of License Amendment Nos. 226 and 214 Adoption of TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control - RITSTF Initiative 5B ML22357A1002023-03-31031 March 2023 and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Issuance of Amendments Standard Emergency Plan and Consolidated Emergency Operations Facility ML22300A2232022-11-0101 November 2022 Issuance of Amendments 241 and 229 TSTF-577 Revised Frequencies for Steam Generator Tube Inspections ML22181A0002022-08-17017 August 2022 Issuance of Amendments Reactor Trip System Power Range Instrumentation Channels ML22188A0852022-07-15015 July 2022 Correction Letter for Amendments 238 and 226 to Renewed Facility Operating Licenses ML22061A2062022-04-0101 April 2022 Issuance of Amendments TSTF-471, Rev. 1, TSTF-571-T, and Administrative Changes to Technical Specification Section 5.0 ML21312A0212021-11-23023 November 2021 Issuance of Amendment Nos. 237 and 225 Inoperable Cooling Water System Supply Header ML21008A0012021-03-19019 March 2021 Issuance of Amendment Nos. 236 and 224 Low Temperature Overpressure Protection 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 ML20283A3422020-11-18018 November 2020 Issuance of Amendment Nos. 233 and 221 Adoption of Technical Specifications Task Force Traveler TSTF-547, Clarification of Rod Position Requirements ML20217L1852020-10-0202 October 2020 Issuance of Amendment Nos. 232 and 220 Increase the Integrated Leak Rate Test Program Type a and Type C Test Frequency 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 ML19276F6842019-11-12012 November 2019 Issuance of Amendments 230 and 218 Issuance of Amendments Adoption of 10 CFR 50.69 - Risk Informed Caterization and Treatment of Structure, Systems and Components of Nuclear Power Reactors ML19232A1512019-11-0707 November 2019 Issuance of Amendments Modifying the Design Basis for Quality Classification of Certain Fuel Handling Equipment ML19255H2012019-09-19019 September 2019 Correction Letter for Amendment Nos. 228 and 216 to Renewed Facility Operating License Nos. DPR-42 and DPR-60 ML19225D2172019-08-24024 August 2019 Correction Letter for Amendment Nos 228 and 216 to Renewed Facility Operating License Nos. DPR-42 and DPR-60 ML19140A4472019-07-30030 July 2019 Issuance of Amendments Revision to National Fire Protection Association (NFPA) Standard NFPA 805 Modifications ML19128A1332019-06-0606 June 2019 Issuance of Amendments TSTF-439 Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO 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) ML18100A7882018-05-0101 May 2018 Issuance of Amendment Special Heavy Lifting Device Nondestructive Examination Frequency (CAC Nos. MG0072 and MG0073; EPID L-2017-LLA-0280) ML17346A3612018-03-0606 March 2018 Issuance of Amendment Nos. 224 and 211 to Adopt Changes to the Emergency Plan 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) ML17334A1782017-11-30030 November 2017 Issuance of Amendment Request Related to Spent Fuel Pool Criticality Technical Specification Changes (CAC Nos. MF7121 and MF7122, EPID L-2015-LLA-0002) Non-Proprietary ML17310B2392017-11-28028 November 2017 and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Issuance of Amendment Unit Staff Qualifications (CAC Nos. MF9545, MF9546, and MF9547; EPID L-2017-LLA-0195) ML17163A0272017-08-0808 August 2017 Issuance of Amendments Transition to NFPA-805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants ML17130A7162017-06-20020 June 2017 Issuance of Amendments Technical Specification 3.8.7 Inverters-Operating ML16256A5142016-10-13013 October 2016 Issuance of Amendment One-Time Extension for Technical Specification Surveillance Requirement 3.8.4.3. DC Sources - Operating 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 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 ML14239A2572014-11-28028 November 2014 and Prairie Island Nuclear Generation Plant, Units 1 and 2 - Issuance of License Amendments Regarding Cyber Security Plan Implementation Schedule Milestones ML14296A6662014-11-19019 November 2014 Issuance of Amendments Regarding Nuclear Methodology References ML13270A2792014-01-25025 January 2014 Issuance of Amendments Emergency Plan Changes ML13175A2082013-09-11011 September 2013 Issuance of Amendment Exception to Technical Specification 5.5.14 Testing Requirements Associated with Steam Generator Replacement ML13241A3832013-08-29029 August 2013 Issuance of Amendments Spent Fuel Pool Criticality Changes ML13113A4002013-07-0202 July 2013 License Amendments TSTF-510 ML13093A3442013-05-0909 May 2013 License Amendments for Fuel Oil System and TSTF-501 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. ML1122008562011-10-27027 October 2011 Operating Plant, Units 1 and 2 - Issuance of Amendments Request to Exclude the Dynamic Effects Associated with Certain Postulated Pipe Ruptures from the Licensing Basis Based Upon Application of Leak-Before-Break Methodology ML1119904692011-08-16016 August 2011 Issuance of Amendments Changes to Security Plan ML11187A2312011-07-29029 July 2011 Issuance of Amendment Nos. 202 (for Unit 1) and 189 (for Unit 2) Regarding Cyber Security ML11147A1232011-06-27027 June 2011 Issuance of Renewed Facility Operating Licenses for Prairie Island Nuclear Generating Plant ML11147A1392011-06-27027 June 2011 Enclosure 2: Prairie Island Nuclear Generating Plant, Unit 2, Renewed Facility Operating License ML11147A1372011-06-27027 June 2011 Renewed Facility Operating License ML1034304982011-05-0404 May 2011 Generation Plant, Units 1 and 2 - Issuance of Amendments Use of Beacon Power Distribution Monitoring System (Tac Nos. ME4059 and ME4060) 2024-01-17
[Table view] Category:Safety Evaluation
MONTHYEARML23356A0032024-01-17017 January 2024 Issuance of Amendments Revise Technical Specification 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) ML23215A1672023-12-15015 December 2023 Acceptance of Requested Licensing Action Amendment Request to Revise Surveillance Requirement 3.8.1.2 Note 3 ML23115A4072023-04-26026 April 2023 Correction of License Amendment Nos. 226 and 214 Adoption of TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control - RITSTF Initiative 5B ML22357A1002023-03-31031 March 2023 and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Issuance of Amendments Standard Emergency Plan and Consolidated Emergency Operations Facility ML22300A2232022-11-0101 November 2022 Issuance of Amendments 241 and 229 TSTF-577 Revised Frequencies for Steam Generator Tube Inspections ML22270A3252022-09-30030 September 2022 (Prairie Island), Unit 2 - Authorization and Safety Evaluation for Alternative Request No. RR-08 ML22181A0002022-08-17017 August 2022 Issuance of Amendments Reactor Trip System Power Range Instrumentation Channels ML22166A3892022-07-28028 July 2022 Issuance of Amendments 239 and 227 24-Month Operating Cycle ML22061A2062022-04-0101 April 2022 Issuance of Amendments TSTF-471, Rev. 1, TSTF-571-T, and Administrative Changes to Technical Specification Section 5.0 ML21312A0212021-11-23023 November 2021 Issuance of Amendment Nos. 237 and 225 Inoperable Cooling Water System Supply Header ML21008A0012021-03-19019 March 2021 Issuance of Amendment Nos. 236 and 224 Low Temperature Overpressure Protection 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 ML20283A3422020-11-18018 November 2020 Issuance of Amendment Nos. 233 and 221 Adoption of Technical Specifications Task Force Traveler TSTF-547, Clarification of Rod Position Requirements ML20217L1852020-10-0202 October 2020 Issuance of Amendment Nos. 232 and 220 Increase the Integrated Leak Rate Test Program Type a and Type C Test Frequency ML20276A0032020-10-0202 October 2020 Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI 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 ML20230A0512020-09-0303 September 2020 Reactor Vessel Material Surveillance Capsule Withdrawal Schedules ML20153A4012020-06-0101 June 2020 and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Relief from the Requirements of the ASME Code ML20135G9922020-05-29029 May 2020 and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Relief from the Requirements of the ASME Code ML20134H9582020-05-29029 May 2020 and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Relief from the Requirements of the ASME Code ML19276F6842019-11-12012 November 2019 Issuance of Amendments 230 and 218 Issuance of Amendments Adoption of 10 CFR 50.69 - Risk Informed Caterization and Treatment of Structure, Systems and Components of Nuclear Power Reactors ML19232A1512019-11-0707 November 2019 Issuance of Amendments Modifying the Design Basis for Quality Classification of Certain Fuel Handling Equipment ML19140A4472019-07-30030 July 2019 Issuance of Amendments Revision to National Fire Protection Association (NFPA) Standard NFPA 805 Modifications ML19177A3802019-07-0303 July 2019 Reactor Vessel Material Surveillance Capsule Withdrawal Schedules ML19128A1332019-06-0606 June 2019 Issuance of Amendments TSTF-439 Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO 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 ML19046A1662019-02-25025 February 2019 Relief from the Requirements of the ASME Code 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) ML18270A0152018-10-19019 October 2018 and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Relief from the Requirements of the ASME OM Code ML18100A7882018-05-0101 May 2018 Issuance of Amendment Special Heavy Lifting Device Nondestructive Examination Frequency (CAC Nos. MG0072 and MG0073; EPID L-2017-LLA-0280) ML17346A3612018-03-0606 March 2018 Issuance of Amendment Nos. 224 and 211 to Adopt Changes to the Emergency Plan 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) ML17334A1782017-11-30030 November 2017 Issuance of Amendment Request Related to Spent Fuel Pool Criticality Technical Specification Changes (CAC Nos. MF7121 and MF7122, EPID L-2015-LLA-0002) Non-Proprietary ML17310B2392017-11-28028 November 2017 and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Issuance of Amendment Unit Staff Qualifications (CAC Nos. MF9545, MF9546, and MF9547; EPID L-2017-LLA-0195) ML17163A0272017-08-0808 August 2017 Issuance of Amendments Transition to NFPA-805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants ML17130A7162017-06-20020 June 2017 Issuance of Amendments Technical Specification 3.8.7 Inverters-Operating ML17110A2752017-05-0404 May 2017 Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 ML16320A0212016-11-28028 November 2016 and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Review of Changes to the Northern States Power Company Quality Assurance Topical Report ML16256A5142016-10-13013 October 2016 Issuance of Amendment One-Time Extension for Technical Specification Surveillance Requirement 3.8.4.3. DC Sources - Operating ML16246A2002016-10-0404 October 2016 Request for Relief 1RR-4-11 and 2-RR-4-11 Associated with Certain Inservice Inspection of Component Welds for the Fourth 10-Year Interval 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 ML15196A2132015-08-17017 August 2015 Requests 1-RR-4-9 and 2-RR-4-9 Associated with the Fourth Ten-Year Interval for the Inservice Inspection Program ML15196A2412015-08-12012 August 2015 Requests 1-RR-5-6 and 2-RR-5-6 Associated with the Fifth Ten-Year Interval for the Inservice Inspection Program ML15196A2272015-08-12012 August 2015 Requests 1-RR-5-3 and 2-RR-5-3 Associated with the Fifth Ten-Year Interval for the Inservice Inspection Program ML15196A2212015-08-12012 August 2015 Requests 1-RR-5-1 and 2-RR-5-1 Associated with the Fifth Ten-Year Interval for the Inservice Inspection Program ML15196A4322015-08-0606 August 2015 Requests 1-RR-4-11 and 2-RR-4-11 Associated with the Fourth Ten-Year Interval for the Inservice Inspection Program ML15196A1952015-08-0606 August 2015 Request 2-RR-4-10 Associated with the Fourth Ten-Year Interval for the Inservice Inspection Program 2024-01-17
[Table view] |
Text
July 26, 2002 Mr. Mano Nazar Site Vice President Prairie Island Nuclear Generating Plant Nuclear Management Company, LLC 1717 Wakonade Drive East Welch, MN 55089
SUBJECT:
PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 -
ISSUANCE OF AMENDMENTS RE: CONVERSION TO IMPROVED TECHNICAL SPECIFICATIONS (TAC NOS. MB0695 AND MB0696)
Dear Mr. Nazar:
The Commission has issued the enclosed Amendment No. 158 to Facility Operating License No. DPR-42 and Amendment No. 149 to Facility Operating License No. DPR-60 for the Prairie Island Nuclear Generating Plant, Units 1 and 2, respectively. The amendments consist of changes to the Technical Specifications (TSs) in response to your application dated December 11, 2000, as supplemented by letters dated March 6, June 5, July 3, August 13, August 29, October 15, November 12, and December 12, 2001, and January 25, January 31, February 14, February 15, February 16, March 6, April 11, May 10, May 30, June 7, June 25, and June 28, 2002.
These amendments convert the current TSs (CTS) for Prairie Island Nuclear Generating Plant, Units 1 and 2, to a combined set of improved TSs (ITS) based on NUREG-1431, Revision 1, Standard Technical Specifications, Westinghouse Plants, dated April 1995.
The Nuclear Regulatory Commission (NRC) staff sent the draft safety evaluation (SE) for the ITS conversion to you by letter dated June 3, 2002, for your review to verify its accuracy. You provided comments by letter dated June 25, 2002. The NRC staff reviewed your comments and incorporated them, as appropriate, in the enclosed final SE for the amendments. The draft SE was also revised based on the NRC staffs review after it was issued.
M. Nazar The ITS conversion will become effective as of its date of issuance and shall be implemented by October 31, 2002. If there is a request for amendment submitted prior to implementation of the ITS being completed, it will be necessary to submit separate TS pages for both CTS and ITS with the amendment request.
A copy of our related safety evaluation is also enclosed. The Notice of Issuance will be included in the Commissions biweekly Federal Register notice.
Sincerely,
/RA/
Tae Kim, Senior Project Manager, Section 1 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-282 and 50-306
Enclosures:
- 1. Amendment No. 158 to DPR-42
- 2. Amendment No. 149 to DPR-60
- 3. Safety Evaluation
- 4. Notice of Issuance
M. Nazar The ITS conversion will become effective as of its date of issuance and shall be implemented by October 31, 2002. If there is a request for amendment submitted prior to implementation of the ITS being completed, it will be necessary to submit separate TS pages for both CTS and ITS with the amendment request.
A copy of our related safety evaluation is also enclosed. The Notice of Issuance will be included in the Commissions biweekly Federal Register notice.
Sincerely,
/RA/
Tae Kim, Senior Project Manager, Section 1 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-282 and 50-306
Enclosures:
- 1. Amendment No. 158 to DPR-42
- 2. Amendment No. 149 to DPR-60
- 3. Safety Evaluation
- 4. Notice of Issuanc DISTRIBUTION PUBLIC OGC RDennig PDIII-1 Reading ACRS CSchulten LRaghavan WBeckner TKim GHill(4)
RBouling RLanksbury, RGN-III ADAMS ACCESSION NO.: Letter/Amendments: ML022070613 Safety Evaluation: ML022070654 Notice: ML022070658 Package: ML022070661 TS pages 1: ML022210043 2: ML022210054 TS Bases 1: ML022140359 2: ML022140370 3: ML022140394 4: ML022140412
- No legal objection w/comments
- Previously Concurred OFFICE PDIII-1/PM PDIII-1/LA RTSB/SC* OGC** PDIII-1/SC NAME TKim RBouling RDennig RWeisman LRaghavan DATE 07/05/02 07/05/02 07/03/02 07/26/02 07/26/02 OFFICIAL RECORD COPY
Prairie Island Nuclear Generating Plant, Units 1 and 2 cc: w/o Technical Specifications J. E. Silberg, Esquire Tribal Council Shaw, Pittman, Potts and Trowbridge Prairie Island Indian Community 2300 N Street, N. W. ATTN: Environmental Department Washington, DC 20037 5636 Sturgeon Lake Road Welch, MN 55089 Site Licensing Manager Prairie Island Nuclear Generating Plant Mr. Roy A. Anderson Nuclear Management Company, LLC Executive Vice President and 1717 Wakonade Drive East Chief Nuclear Officer Welch, MN 55089 Nuclear Management Company, LLC 700 First Street Adonis A. Neblett Hudson, WI 54016 Assistant Attorney General Office of the Attorney General Nuclear Asset Manager 455 Minnesota Street Xcel Energy, Inc.
Suite 900 414 Nicollet Mall St. Paul, MN 55101-2127 Minneapolis, MN 55401 U.S. Nuclear Regulatory Commission Resident Inspectors Office 1719 Wakonade Drive East Welch, MN 55089-9642 Regional Administrator, Region III U.S. Nuclear Regulatory Commission 801 Warrenville Road Lisle, IL 60532-4351 Administrator Goodhue County Courthouse Box 408 Red Wing, MN 55066-0408 Commissioner Minnesota Department of Commerce 121 Seventh Place East Suite 200 St. Paul, MN 55101-2145 NOTE: To receive a copy of the Technical Specifications, please call T. J. Kim at (301) 415-1392.
March 2002
NUCLEAR MANAGEMENT COMPANY, LLC DOCKET NO. 50-282 PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 158 License No. DPR-42
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Nuclear Management Company, LLC (the licensee), dated December 11, 2000, as supplemented by letters dated March 6, June 5, July 3, August 13, August 29, October 15, November 12, and December 12, 2001, and January 25, January 31, February 14, February 15, February 16, March 6, April 11, May 10, May 30, June 7, June 25, and June 28, 2002, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.
- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-42 is hereby amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 158, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
Also, the license is amended by changes to Appendix B of Facility Operating License No. DPR-42 and paragraph 2.C.(5) is hereby amended to read as follows:
Additional Conditions The Additional Conditions contained in Appendix B, as revised through Amendment No. 158, are hereby incorporated into this license. NMC shall operate the facility in accordance with the Additional Conditions.
Appendix B is amended to add the following paragraphs:
(1) The schedule for performing Surveillance Requirements (SRs) that are new or revised in Amendment No. 158 shall be as follows:
For SRs that are new in this amendment, the first performance is due at the end of the first surveillance interval, which begins on the date of implementation of this amendment.
For SRs that existed prior to this amendment, whose intervals of performance are being reduced, the first reduced surveillance interval begins upon completion of the first surveillance performed after implementation of this amendment.
For SRs that existed prior to this amendment that have modified acceptance criteria, the first performance is due at the end of the surveillance interval that began on the date the surveillance was last performed prior to the implementation of this amendment.
For SRs that existed prior to this amendment, whose intervals of performance are being extended, the first extended surveillance interval begins upon completion of the last surveillance performed prior to the implementation of this amendment.
(2) The licensee is authorized to relocate certain Technical Specification requirements previously included in Appendix A to licensee-controlled documents, as described in Table LR, "Less Restrictive Changes - Relocated Details," and Table R, "Relocated Specifications," attached to the NRC staffs safety evaluation dated July 26, 2002. Those requirements shall be relocated to the appropriate documents no later than October 31, 2002.
(3) The licensee will complete evaluation of the maximum test face velocity for the ventilation systems included in Technical Specifications (TS) Section 5.5.9 by February 28, 2003. The licensee will also submit a license amendment request for TS amendment by February 28, 2003, to specify the maximum test face velocity if the maximum actual face velocity is greater than 110 percent of 40 fpm based on the licensees evaluation.
- 3. This license amendment is effective as of its date of its issuance and shall be implemented by October 31, 2002.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
L. Raghavan, Chief, Section 1 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation Attachments: Changes to the Operating License and Technical Specifications Date of Issuance: July 26, 2002
ATTACHMENT TO LICENSE AMENDMENT NO. 158 FACILITY OPERATING LICENSE NO. DPR-42 DOCKET NO. 50-282 Replace the following page of Facility Operating License No. DPR-42 with the attached revised page. The revised page is identified by amendment number and contains a marginal line indicating the area of change.
REMOVE INSERT
- Appendix B (Page B-2)
Replace the following pages of the Appendix A Technical Specifications with the attached pages. The pages are identified by amendment numbers.
REMOVE INSERT Current TSs (in their entirety) Improved TSs (in their entirety)
NUCLEAR MANAGEMENT COMPANY, LLC DOCKET NO. 50-306 PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 149 License No. DPR-60
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Nuclear Management Company, LLC (the licensee), dated December 11, 2000, as supplemented by letters dated March 6, June 5, July 3, August 13, August 29, October 15, November 12, and December 12, 2001, and January 25, January 31, February 14, February 15, February 16, March 6, April 11, May 10, May 30, June 7, June 25, and June 28, 2002, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.
- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-60 is hereby amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 149, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
Also, the license is amended by changes to Appendix B of Facility Operating License No. DPR-60 and paragraph 2.C.(5) is hereby amended to read as follows:
Additional Conditions The Additional Conditions contained in Appendix B, as revised through Amendment No. 149, are hereby incorporated into this license. NMC shall operate the facility in accordance with the Additional Conditions.
Appendix B is amended to add the following paragraphs:
(1) The schedule for performing Surveillance Requirements (SRs) that are new or revised in Amendment No. 149 shall be as follows:
For SRs that are new in this amendment, the first performance is due at the end of the first surveillance interval, which begins on the date of implementation of this amendment.
For SRs that existed prior to this amendment, whose intervals of performance are being reduced, the first reduced surveillance interval begins upon completion of the first surveillance performed after implementation of this amendment.
For SRs that existed prior to this amendment that have modified acceptance criteria, the first performance is due at the end of the surveillance interval that began on the date the surveillance was last performed prior to the implementation of this amendment.
For SRs that existed prior to this amendment, whose intervals of performance are being extended, the first extended surveillance interval begins upon completion of the last surveillance performed prior to the implementation of this amendment.
(2) The licensee is authorized to relocate certain Technical Specification requirements previously included in Appendix A to licensee-controlled documents, as described in Table LR, "Less Restrictive Changes - Relocated Details," and Table R, "Relocated Specifications," attached to the NRC staffs safety evaluation dated July 26, 2002. Those requirements shall be relocated to the appropriate documents no later than October 31, 2002.
(3) The licensee will complete evaluation of the maximum test face velocity for the ventilation systems included in Technical Specifications (TS) Section 5.5.9 by February 28, 2003. The licensee will also submit a license amendment request for TS amendment by February 28, 2003, to specify the maximum test face velocity if the maximum actual face velocity is greater than 110 percent of 40 fpm based on the licensees evaluation.
- 3. This license amendment is effective as of its date of its issuance and shall be implemented by October 31, 2002.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
L. Raghavan, Chief, Section 1 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation Attachments: Changes to the Operating License and Technical Specifications Date of Issuance: July 26, 2002
ATTACHMENT TO LICENSE AMENDMENT NO. 149 FACILITY OPERATING LICENSE NO. DPR-60 DOCKET NO. 50-306 Replace the following page of Facility Operating License No. DPR-60 with the attached revised page. The revised page is identified by amendment number and contains a marginal line indicating the area of change.
REMOVE INSERT
- Appendix B (Page B-2)
Replace the following pages of the License and Appendix A Technical Specifications with the attached pages. The pages are identified by amendment numbers.
REMOVE INSERT Current TSs (in their entirety) Improved TSs (in their entirety)
APPENDIX B ADDITIONAL CONDITIONS FACILITY OPERATING LICENSE NO. DPR-42 Amendment Implementation Number Additional Conditions Date 158 The schedule for performing Surveillance Requirements October 31, (SRs) that are new or revised in Amendment No. 158 shall 2002 be as follows:
For SRs that are new in this amendment, the first performance is due at the end of the first surveillance interval, which begins on the date of implementation of this amendment.
For SRs that existed prior to this amendment, whose intervals of performance are being reduced, the first reduced surveillance interval begins upon completion of the first surveillance performed after implementation of this amendment.
For SRs that existed prior to this amendment that have modified acceptance criteria, the first performance is due at the end of the surveillance interval that began on the date the surveillance was last performed prior to the implementation of this amendment.
For SRs that existed prior to this amendment, whose intervals of performance are being extended, the first extended surveillance interval begins upon completion of the last surveillance performed prior to the implementation of this amendment.
158 The licensee is authorized to relocate certain Technical October 31, Specification requirements previously included in 2002 Appendix A to licensee-controlled documents, as described in Table LR, "Less Restrictive Changes - Relocated Details," and Table R, "Relocated Specifications," attached to the NRC staffs safety evaluation dated .
Those requirements shall be relocated to the appropriate documents no later than October 31, 2002.
158 The licensee will complete evaluation of the maximum test February 28, face velocity for the ventilation systems included in 2003 Technical Specifications (TS) Section 5.5.9 by February 28, 2003. The licensee will also submit a license amendment request for TS amendment by February 28, 2003, to specify the maximum test face velocity if the maximum actual face velocity is greater than 110 percent of 40 fpm based on the licensees evaluation.
B-2 Amendment No. 158 l
APPENDIX B ADDITIONAL CONDITIONS FACILITY OPERATING LICENSE NO. DPR-60 Amendment Implementation Number Additional Conditions Date 149 The schedule for performing Surveillance Requirements October 31, (SRs) that are new or revised in Amendment No. 149 shall 2002 be as follows:
For SRs that are new in this amendment, the first performance is due at the end of the first surveillance interval, which begins on the date of implementation of this amendment.
For SRs that existed prior to this amendment, whose intervals of performance are being reduced, the first reduced surveillance interval begins upon completion of the first surveillance performed after implementation of this amendment.
For SRs that existed prior to this amendment that have modified acceptance criteria, the first performance is due at the end of the surveillance interval that began on the date the surveillance was last performed prior to the implementation of this amendment.
For SRs that existed prior to this amendment, whose intervals of performance are being extended, the first extended surveillance interval begins upon completion of the last surveillance performed prior to the implementation of this amendment.
149 The licensee is authorized to relocate certain Technical October 31, Specification requirements previously included in 2002 Appendix A to licensee-controlled documents, as described in Table LR, "Less Restrictive Changes - Relocated Details," and Table R, "Relocated Specifications," attached to the NRC staffs safety evaluation dated .
Those requirements shall be relocated to the appropriate documents no later than October 31, 2002.
149 The licensee will complete evaluation of the maximum test February 28, face velocity for the ventilation systems included in 2003 Technical Specifications (TS) Section 5.5.9 by February 28, 2003. The licensee will also submit a license amendment request for TS amendment by February 28, 2003, to specify the maximum test face velocity if the maximum actual face velocity is greater than 110 percent of 40 fpm based on the licensees evaluation.
B-2 Amendment No. 149 l