|
---|
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] 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
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 December 1, 2011 Mr. Mark A. Schimmel Site Vice President Prairie Island Nuclear Generating Plant Northern States Power Company - Minnesota 1717 Wakonade Drive East Welch, MN 55089-9642 SUB~IECT: PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 - ISSUANCE OF AMENDMENTS RE: REVISION OF TECHNICAL SPECIFICATION 5.2.1, "ONSITE AND OFFSITE ORGANIZATIONS" AND TS 5.3, "PLANT STAFF QUALIFICATIONS" (TAC NOS. ME5447 AND ME5448)
Dear Mr. Schimmel:
The U.S. Nuclear Regulatory Commission has issued the enclosed Amendment No. 205 to Renewed Facility Operating License No. DPR42 and Amendment No. 192 to Renewed 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 February 4, 2011 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML110390081).
The amendments make administrative changes to TSs 5.2.1 and 5.3 that: (1) allow certain requirements of onsite and offsite organizations to be documented in the Quality Assurance Topical Report (QATR); and (2) remove reference to specific education and experience requirements for operator license applicants.
M. A. Schimmel - 2 A copy of our related safety evaluation is also enclosed. The Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
Sincerely,
~=R'~(}-~
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
Enclosures:
- 1. Amendment No. 205 to DPR-42
- 2. Amendment No. 192 to DPR-60
- 3. Safety Evaluation cc w/encls: Distribution via ListServ
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 NORTHERN STATES POWER COMPANY - MINNESOTA DOCKET NO. 50-282 PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 205 License No. DPR-42
- 1. The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Northern States Power Company, a Minnesota Corporation (NSPM, the licensee), dated February 4,2011, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's 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 Commission's 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 p.art 51 of the Commission's 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 Renewed Facility Operating License No. DPR-42 is hereby amended to read as follows:
- 2 Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 205 , are hereby incorporated in the renewed operating license.
NSPM shall operate the facility in accordance with the Technical Specifications.
- 3. This license amendment is effective as of the date of its issuance and shall be implemented within 90 days.
FOR THE NUCLEAR REGULATORY COMMISSION
~
Robert J. p~scarelli, c:!7 Plant Licensing Branch 111-1 r
Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Renewed Facility Operating License and Technical Specifications Date of Issuance: December 1, 2.011
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 NORTHERN STATES POWER COMPANY - MINNESOTA DOCKET NO. 50-306 PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment NO.192 License No. DPR-60
- 1. The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Northern States Power Company, a Minnesota Corporation (NSPM, the licensee), dated February 4, 2011, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's 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 Commission's regulations; O. 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 Commission's 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 Renewed Facility Operating License No. OPR-60 is hereby amended to read as follows:
-2 Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 192 are hereby incorporated in the renewed operating license.
I NSPM shall operate the facility in accordance with the Technical Specifications.
- 3. This license amendment is effective as of the date of its issuance and shall be implemented within 90 days.
FOR THE NUCLEAR REGULATORY COMMISSION Robert J. Pascarelli, Chi:;iif Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Renewed Facility Operating License and Technical Specifications Date of Issuance: 1)ccenber 1, 2011
ATTACHMENT TO LICENSE AMENDMENT NOS. 205 AND 192 RENEWED FACILITY OPERATING LICENSE NOS. DPR-42 AND DPR-50 DOCKET NOS. 50-282 AND 50-305 Replace the following pages of the Renewed Facility Operating License Nos. DPR-42 and DPR-50 with the attached revised pages. The changed areas are identified by a marginal line.
REMOVE INSERT DPR-42, License Page 3 DPR-42, License Page 3 DPR-50, License Page 3 DPR-50, License Page 3 Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
REMOVE INSERT 5.0-2 5.0-2 5.0-5 5.0-5
-3 (3) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, NSPM to receive, possess, and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, NSPM to receive, possess and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument and equipment calibration or associated with radioactive apparatus or components; (5) Pursuant to the Act and 10 CFR Parts 30 and 70, NSPM to possess but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility; (6) Pursuant to the Act and 10 CFR Parts 30 and 70, NSPM to transfer byproduct materials from other job sites owned by NSPM for the purpose of volume reduction and decontamination.
C. This renewed operating license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I:
Part 20, Section 30.34 of Part 30, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1) Maximum Power Level NSPM is authorized to operate the facility at steady state reactor core power levels not in excess of 1677 megawatts thermal.
(2) Technical Specifications
. The Technical Specifications contained in Appendix A, as revised through Amendment No. 205, are hereby incorporated in the renewed operating license. NSPM shall operate the facility in accordance with the Technical Specifications.
(3) Physical Protection NSPM shall fully implement and maintain in effect all provisions of the Commission-approved physical security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans, which contains Renewed Operating License No. DPR-42 Amendment No. 205
- 3 (3) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, NSPM to receive, possess, and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, NSPM to receive, possess and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument and equipment calibration or associated with radioactive apparatus or components; (5) Pursuant to the Act and 10 CFR Parts 30 and 70, NSPM to possess but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility; (6) Pursuant to the Act and 10 CFR Parts 30 and 70, NSPM to transfer byproduct materials from other job sites owned by NSPM for the purposes of volume reduction and decontamination.
C. This renewed operating license shall be deemed to contain and is Subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I:
Part 20, Section 30.34 of Part 30, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1) Maximum Power Level NSPM is authorized to operate the facility at steady state reactor core power levels not in excess of 1677 megawatts thermal.
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 192, are hereby incorporated in the renewed operating license.
NSPM shall operate the facility in accordance with the Technical Specifications.
(3) Physical Protection NSPM shall fully implement and maintain in effect all provisions of the Commission-approved physical security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans, which contains Renewed Operating License No. DPR-60 Amendment No. 192
Organization 5.2 5.0 ADMlNISTRATIVE CONTROLS 5.2 Organization 5.2.1 Onsite and Offsite Organizations Onsite and offsite organizations shall be established for plant operation and corporate management, respectively. The onsite and offsite organizations shall include the positions for activities affecting safety of the nuclear power plant.
- a. Lines of authority, responsibility, and communication shall be defined and established throughout highest management levels, intermediate levels, and all operating organization positions. These relationships shall be documented and updated, as appropriate, in organization charts, fimctional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent fonns of documentation. These requirements, including the plant specific titles of those personnel fulfilling the responsibilities of the positions delineated in these Technical Specifications, shall be documented in the Updated Safety Analysis Report (USAR) or Quality Assurance Topical Report;
- b. The plant manager shall be responsible for overall safe operation of the plant and shall have control over those onsite activities necessary for safe operation and maintenance ofthe plant;
- c. A corporate officer shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable perfonnance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety; and
- d. The individuals who train the operating staff, carry out health physics, or perfonn quality assurance fimctions may report to the appropriate onsite manager; however, these individuals shall have sufficient organizational freedom to ensure their independence from operating pressures.
Prairie Island Unit I - Amendment No. -J-S.8 205 Units I and 2 5.0-2 Unit 2 Amendment No. -l49 192
Plant Staff Qualifications 5.3 5.0 ADMINISTRATIVE CONTROLS 5.3 Plant Staff Qualifications 5.3.1 Each member of the plant staff shaH meet or exceed the minimum qualifications of Regulatory Guide 1.8, Revision 1, September 1975 except for the operations manager who shall meet the requirements of ANSI N18.1-1971, except that NRC license requirements are as specified in TS 5.2.2.e.
5.3.2 For the purpose of 10 CFR 55.4, a licensed senior reactor operator (SRO) and a licensed reactor operator (RO) are those individuals who, in addition to meeting the requirements ofTS 5.3.1, perform the functions described in 10 CFR 50.54(m).
Prairie Island Unit 1- Amendment No. +M +&8 205 Units 1 and 2 5.0-5 Unit 2 - Amendment No. ++4 W 192
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 205 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-42 AND AMENDMENT NO. 192 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-60 NORTHERN STATES POWER COMPANY - MINNESOTA PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 DOCKET NOS. 50-282 AND 50-306
1.0 INTRODUCTION
By application dated February 4,2011 (Agencywide Documents Access and Management System Accession No. ML110390081), Northern States Power Company, a Minnesota Corporation (NSPM, the licensee), requested changes to the Technical Specifications (TSs) for the Prairie Island Nuclear Generating Plant (PINGP), Units 1 and 2. The proposed changes would make administrative changes to TS 5.2.1 and 5.3 that: (1) allow certain requirements of onsite and offsite organizations to be documented in the Quality Assurance Topical Report (QATR); and (2) remove reference to specific education and experience requirements for operator license applicants.
Specifically, the proposed changes would revise PINGP, Units 1 and 2, TS Section 5.0, "Administrative Controls," by (1) revising TS 5.2.1(a) by adding the QATR as an allowable location for documentation of requirements for lines of authority, responsibility, and communications; and (2) revising TS 5.3.1 by the removal of the exception to operator license applicants' education and experience requirements, and the reference to a letter which references a specific industry guidance document. The proposed revision to TS 5.3.1 will update staff qualifications and make them consistent with the licensee's other operating nuclear power plant (Monticello Nuclear Generating Plant (MNGP>>.
2.0 REGULATORY EVALUATION
Section 182a of the Atomic Energy Act requires applicants for nuclear power plant operating licenses to include TSs as part of the license. In Title 10 of the Code of Federal Regulations (10 CFR), Section 50.36, the Commission established regulatory requirements related to the content of TSs. This regulation requires that the TSs include items in eight specific categories.
These categories include 1) safety limits, limiting safety systems settings, and limiting control Enclosure
- 2 settings, 2) limiting conditions for operation (LCO), 3) surveillance requirements (SRs), 4) design features, 5) administrative controls, 6) decommissioning, 7) initial notification, and 8) written reports. The regulation does not specify the particular requirements to be included in a plant's TSs. However, the Nuclear Regulatory Commission (NRC) has approved Standard Technical Specifications (STS) for each reactor type and encourages licensees to upgrade their TS consistent with the regulations and conforming, to the extent practicable, to Revision 3 with incorporated Travelers to the improved STS.
The NRC developed criteria, as described in the "Final Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors" (58 FR 39132), to determine which design conditions and associated surveillances should be located in the TSs as LCOs. Four criteria were subsequently incorporated into the regulations by an amendment to 10 CFR 50.36 (60 FR 36953).
The Commission's Final Policy Statement and documentation related to the revision of 10 CFR 50.36 acknowledged that implementation of the four criteria may permit some requirements presently in the TSs to be relocated to other licensee-controlled documents and programs.
Licensees may propose revisions to the TS to adopt STS format and content provided that plant specific review supports a finding of continued adequate safety because: (1) the change is editorial, administrative or provides clarification (Le., no requirements are materially altered),
(2) the change is more restrictive than the licensee's current requirement, or (3) the change is less restrictive than the licensee's current requirement, but nonetheless still affords adequate assurance of safety when judged against current regulatory standards. The NRC staff reviews such proposals and decides whether or not to change the licensee's TS.
On December 12,1995, the NRC issued Administrative Letter (AL) 95-06, "Relocation of Technical Specification Administrative Controls Related to Quality Assurance," to inform licensees of experiences involving the relocation of TS administrative controls related to quality assurance. In AL 95-06, the NRC staff identified typical TS administrative controls that may be relocated to licensee quality assurance control documents subject to the controls of 10 CFR 50.54{a). TS administrative control requirements identified in AL 95-06 include the independent safety engineering group, reviews and audits, the procedure review process, and records and record retention.
The NRC staff reviewed the TSs proposed to be relocated for compliance with 10 CFR 50.36 and agreement with staff guidance as established in NUREG-1431, Rev. 3, "Standard Technical Specifications, Westinghouse Plants," for Pressurized Water Reactors (PWRs).
On March 20, 1985, the NRC issued the Commission Policy Statement on Training and Qualification of Nuclear Power Plant Personnel, which endorsed the National Academy for Nuclear Training (NANT) and the training accreditation process. In Generic Letter 87-07, "Information Transmittal of Final Rulemaking for Revisions to Operator Licensing - 10 CFR 55 and Conforming Amendments," dated March 19,1987, and in NUREG-1262, "Answers to Questions at Public Meetings Regarding Implementation of Title 10, Code of Federal Regulations, Part 55 on Operators' Licenses," published November 1987. the NRC indicated it would accept a facility's licensed operator training program if the facility certified in writing that
- 3 the program was accredited and based on a systems approach to training (SAT). This certification would supersede the requirements of ANSI N18.1-1971, "Selection and Training of Nuclear Power Plant Personnel," and ANSI/ANS-3.1-1978, "Selection, Qualification and Training of Personnel for Nuclear Power Plants." Facility licensees were advised to submit a request to the NRC for an administrative change to their licensing documents to revise or delete, as appropriate, the requirements that had been superseded.
In 1992, the NRC published its proposed rule 10 CFR 50.120, "Training and Qualification of Nuclear Power Plant PersonneL" The proposed rule stated that, if adopted, the rule would supersede the Policy Statement on Training and Qualification of Nuclear Power Plant Personnel and would not result in any change to accredited programs. The Commission concluded that accredited programs, implemented consistent with industry objectives and criteria, would be in compliance with this regulation. In April 1993, the NRC published its final rule on training and qualification of nuclear power plant personnel. The rule requires nuclear power plant licensees to establish, implement, and maintain SAT-based training programs for nine categories of nuclear power plant personnel. Accreditation of these nine training programs is an acceptable means of meeting the requirements of 10 CFR 50.120.
On January 18, 2001, the NRC published NRC Regulatory Issue Summary (RIS) 2001-01, "Eligibility of Operator License Applicants," to familiarize licensees with the NRC's current guidelines for the qualification and training of operator and senior operator license applicants.
RIS 2001-01 acknowledged that 10 CFR 55.31 (a)(4) allows the NRC to accept an application for an operator's license if the facility licensee certifies that the applicant has successfully completed a Commission approved training program that is based on SAT. In addition, RIS 2001-01 stated that: (1) a training program would be considered approved by the NRC when it receives or renews accreditation from the National Nuclear Accrediting Board (NNAB);
(2) accreditation of operator training programs suggests that facilities are implementing the education and experience guidelines endorsed by the NNAB; (3) NANT guidelines for education and experience (those in effect in 1987 or those issued in January 2000) outline acceptable methods for implementing the Commission's regUlations; and (4) the staff encourages all facility licensees to review their requirements and commitments related to operator and senior operator education and experience and to update their documentation (e.g., Final Safety Analysis Report, Technical SpeCifications, and training program descriptions) to "enhance consistency and minimize confusion."
3.0 TECHNICAL EVALUATION
3.1 Proposed Changes to TS 5.2.1! Onsite and Offsite Organizations Section 5.0 of the PINGP TSs contain administrative controls reqUirements in accordance with 10 CFR 50.36(c)(5). In its application, the licensee proposed to revise TS 5.2.1 (a) by including the QATR as an allowable location for documenting the requirements for lines of authority, responsibility, and communications. The licensee stated that the addition of the QATR would allow a document common to PINGP and MNGP to contain the organizational relationships per TS 5.2.1 (a).
Section 50.36(c)(5) of 10 CFR states, "administrative controls are the provisions relating to organization and management, procedures, recordkeeping, review and audit, and reporting
-4 necessary to assure operation of the facility in a safe manner." TS 5.2.1 contains the requirement for establishing onsite and offsite organizations and positions for activities affecting safety of the nuclear plant. Specifically, 5.2.1 (a) establishes the documented location of lines of authority, responsibility, communications, and specific titles of the personnel.
The NRC staff has reviewed the licensee's proposed changes to TS 5.2.1 (a) against the criteria for administrative controls set forth in 10 CFR 50.36(c)(5). The NRC staff has determined that the content of the proposed changes involve administrative controls related to quality assurance requirements. In addition, the NRC staff determined that the addition of the wording "or Quality Assurance Topical Report" is editorial in nature and does not change the meaning of the intended requirements. The relocation requirements will be directly controlled by regulations in accordance with 10 CFR 50.54(a) or 10 CFR 50.59. Further, the NRC staff determined that the proposed changes are consistent with the requirements identified for relocation of the quality assurance plan by AL 95-06 and are also consistent with the guidance in NUREG-1431.
Therefore, the NRC staff concludes that the proposed change to TS 5.2.1 (a) is acceptable.
3.2 Proposed Changes to TS 5.3, Plant Staff Qualifications In its application, the licensee proposed to revise PINGP Units 1 and 2 TS 5.3.1, by removing the exception to operator license applicants' education and experience requirements, and the reference to a letter which references a specific industry guidance document. The proposed revision to TS 5.3.1 will update staff qualifications and make them consistent with the licensee's other operating nuclear power plant (MNGP).
The revision proposed by NSPM will revise PINGP Units 1 and 2 TS Section 5.3, "Plant Staff Qualifications," to remove outdated licensed operator educational and experience requirements, based on NNAB's accreditation of PINGP's licensed operator training programs. This proposed change is consistent with 10 CFR 55(a)(4). In addition, this change will not affect the 10 CFR 50.36(c)(5) requirement to ensure the licensee maintains administrative controls that assure the operation of the facility in a safe manner. Therefore, the NRC staff concludes that the proposed change to TS 5.3.1 is acceptable.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Minnesota State official was notified of the proposed issuance of the amendments. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendments relate to changes in recordkeeping, reporting, or administrative procedures or requirements. Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(1 0). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.
- 5
6.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributors: S. Anderson, NRR S. Currie, NRR Date: December 1, 2011
M. A. Schimmel -2 A copy of our related safety evaluation is also enclosed. The Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
Sincerely, IRA!
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
Enclosures:
- 1. Amendment No. 205 to DPR-42
- 2. Amendment No. 192 to DPR-60
- 3. Safety Evaluation cc w/encls: Distribution via ListServ DISTRIBUTION:
PUBLIC LPL3-1 r/f RidsNrrDorlLpl3-1 Resource RidsOgcRp Resource RidsNrrPMPrairielsland Resource RidsNrrLABTully Resource RidsNrrDirslolb Resource RidsAcrsAcnw MailCTR Resource RidsNrrDirsltsb Resource SCurrie, NRR RidsRgn3MailCenter Resource RidsNrrDorlDpr Resource SAnderson, NRR ADAMS Accession No'.. ML112901115 *via memo OFFICE LPL3-11 PM LPL3-1/LA DIRS/IOLB/BC* DIRS/ITSB/BC*
NAME TWengert BTully JMcHaie RElliott DATE 11/16/11 11/15/11 06/24/11 07/14/11 OFFICE OGC/NLO NRRlLPL3-1/BC(A) NRR/LPL3-1/PM NAME BMizuno TBeitz TWengert DATE 11/18111 12/1/11 12/1/11 OFFICIAL RECORD COpy