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MONTHYEARML0313306832003-05-14014 May 2003 Notice of Meeting with Nuclear Management Company, LLC License Amendment Request Dated March 25, 2003, for Transition of Safety Analyses at Prairie Island Project stage: Meeting ML0315305802003-05-30030 May 2003 Safety Analyses Transition - LAR Submitted March 25, 2003, NRC-NMC May 20, 2003 Project stage: Other ML0315303402003-05-30030 May 2003 Summary of Meeting with Nuclear Management Co, LLC Regarding License Amendment Request Dated March 25, 2003 for Transition of Safety Analyses at Prairie Island Nuclear Generating Plant, Units 1 and 2 Project stage: Meeting ML0332105222003-11-26026 November 2003 Request for Additional Information Re Proposed Amendment Request for Safety Analyses Transition Project stage: RAI ML0406803922004-02-11011 February 2004 Supplement to License Amendment Request (LAR) Dated March 25, 2003, Regarding Safety Analyses Transition Project stage: Supplement ML0404205732004-02-12012 February 2004 Request for Additional Information Re License Amendment Request Project stage: RAI L-PI-04-027, Supplement to License Amendment Request Dated 03/25/03 Regarding Safety Analyses Transition2004-02-23023 February 2004 Supplement to License Amendment Request Dated 03/25/03 Regarding Safety Analyses Transition Project stage: Supplement L-PI-04-049, Prairie Units 1 and 2, Revised Page for License Amendment Request (LAR) Dated March 25, 2003, Safety Analysis Transition2004-04-0707 April 2004 Prairie Units 1 and 2, Revised Page for License Amendment Request (LAR) Dated March 25, 2003, Safety Analysis Transition Project stage: Request ML0409902512004-04-13013 April 2004 Withholding from Public Disclosure, CAW-04-1779, MB8128 & MB8129 Project stage: Other ML0409902062004-04-14014 April 2004 4/16/04, Prairie, Units 1 & 2, Withholding from Public Disclosure, CAW-03-1752 Project stage: Other ML0409002092004-04-28028 April 2004 License Amendment Relaxed Axial Offset Control of Reactor Core Through Technical Specification Changes Project stage: Acceptance Review ML0412102562004-04-28028 April 2004 Technical Specifications for Amd 162 and 153, Respectively Project stage: Other L-PI-04-072, Comments on License Amendment and Safety Evaluation for License Amendment Request (LAR) Dated March 25, 2003, Safety Analyses Transition.2004-06-28028 June 2004 Comments on License Amendment and Safety Evaluation for License Amendment Request (LAR) Dated March 25, 2003, Safety Analyses Transition. Project stage: Request 2004-02-23
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Category:Letter
MONTHYEARML24298A0552024-10-30030 October 2024 Response to Alternative RR-10, Auxiliary Feedwater Valve Testing IR 05000282/20244032024-10-25025 October 2024 – Security Baseline Inspection Report 05000282/2024403 and 05000306/2024403 05000282/LER-2024-001-01, Auxiliary Building Special Ventilation System Inoperable During Movement of Irradiated Fuel Assemblies2024-10-22022 October 2024 Auxiliary Building Special Ventilation System Inoperable During Movement of Irradiated Fuel Assemblies L-PI-24-044, Application to Revise Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program2024-10-21021 October 2024 Application to Revise Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program ML24277A1012024-10-0303 October 2024 Closure of Interim Report of a Potential Deviation or Failure to Comply Associated with Bentley Systems Incorporated Autopipe Software ML24221A3622024-09-27027 September 2024 Issuance of Amendment Nos. 245 and 233 Revise Technical Specification 3.8.1, AC Sources-Operating, Surveillance Requirement 3.8.1.2, Note 3 ML24241A1682024-09-23023 September 2024 Transmittal Letter Amendment No. 13 to Materials License No. Special Nuclear Material-2506 for the Prairie Island Independent Spent Fuel Storage Installation 05000282/LER-2024-001, Auxiliary Building Special Ventilation System Inoperable During Movement of Irradiated Fuel Assemblies2024-09-16016 September 2024 Auxiliary Building Special Ventilation System Inoperable During Movement of Irradiated Fuel Assemblies IR 05000282/20243012024-09-13013 September 2024 NRC Initial License Examination Report 05000282/2024301 and 05000306/2024301 IR 05000282/20240052024-08-28028 August 2024 Updated Inspection Plan and Assessment Follow-Up Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report 05000282/2024005 and 05000306/2024005) L-PI-24-040, Post-Submittal Package Letter2024-08-23023 August 2024 Post-Submittal Package Letter IR 05000282/20245012024-08-0505 August 2024 Emergency Preparedness Inspection Report 05000282/2024501 and 05000306/2024501 ML24213A1592024-07-31031 July 2024 Operator Licensing Examination Approval - Prairie Island Nuclear Generating Plant IR 05000282/20240022024-07-30030 July 2024 Integrated Inspection Report 05000282/2024002 and 05000306/2024002 ML24208A1502024-07-26026 July 2024 Independent Spent Fuel Storage Installation - Submittal of Quality Assurance Topical Report (NSPM-1) ML24197A2012024-07-15015 July 2024 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000282/2024004 IR 05000282/20240102024-06-28028 June 2024 Comprehensive Engineering Team Inspection Report 05000282/2024010 and 05000306/2024010 L-PI-24-036, – Preparation and Scheduling of Operator Licensing Examinations2024-06-28028 June 2024 – Preparation and Scheduling of Operator Licensing Examinations ML24158A5912024-06-0606 June 2024 CFR 50.46 LOCA Annual Report L-PI-24-031, Independent Spent Fuel Storage Installation, Supplement to License Amendment Request to Revise Independent Spent Fuel Storage Installation (ISFSI) License Conditions 23(a), 24(A)(2), and 24(B)(2)2024-06-0505 June 2024 Independent Spent Fuel Storage Installation, Supplement to License Amendment Request to Revise Independent Spent Fuel Storage Installation (ISFSI) License Conditions 23(a), 24(A)(2), and 24(B)(2) L-PI-24-014, License Amendment Request to Revise the Technical Specification Definition of Reactor Trip System (RTS) Response Time and Apply Response Time Testing to RTS Trip Functions with Time Delay Assumption2024-06-0303 June 2024 License Amendment Request to Revise the Technical Specification Definition of Reactor Trip System (RTS) Response Time and Apply Response Time Testing to RTS Trip Functions with Time Delay Assumption 05000306/LER-2024-001-01, Reactor Trip and Auto-Start Actuation of Auxiliary Feedwater Due to Loss of Suction to the 22 Main Feedwater Pump2024-05-31031 May 2024 Reactor Trip and Auto-Start Actuation of Auxiliary Feedwater Due to Loss of Suction to the 22 Main Feedwater Pump ML24155A1922024-05-31031 May 2024 Refueling Outage Unit 2 R33 Owners Activity Report for Class 1, 2, 3 and Mc Inservice Inspections ML24262A1992024-05-29029 May 2024 L-PI-24-018 PINGP 75 Day Letter ML24149A3712024-05-29029 May 2024 (Ping) - Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection L-PI-24-030, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.8.12024-05-22022 May 2024 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.8.1 ML24141A1292024-05-22022 May 2024 Northern States Power Company - Use of Encryption Software for Electronic Transmission of Safeguards Information ML24141A0452024-05-20020 May 2024 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection ML24128A2572024-05-16016 May 2024 ISFSI A13 Acceptance Letter IR 05000282/20240012024-05-15015 May 2024 Integrated Inspection Report 05000282/2024001 and 05000306/2024001 ML24130A2362024-05-0909 May 2024 Independent Spent Fuel Storage Installation - 2023 Annual Radiological Environmental Monitoring Program Report ML24130A2392024-05-0909 May 2024 2023 Annual Radioactive Effluent Report ML24071A1162024-05-0101 May 2024 Issuance of Amendment Nos. 244 and 232 Revise TS 3.7.8, Cooling Water (Cl) System ML24128A0882024-04-30030 April 2024 Submittal of Updated Safety Analysis Report (Usar), Revision 38 05000306/LER-2024-001, Reactor Trip and Auto-Start Actuation of Auxiliary Feedwater Due to Loss of Suction to the 22 Main Feedwater Pump2024-04-29029 April 2024 Reactor Trip and Auto-Start Actuation of Auxiliary Feedwater Due to Loss of Suction to the 22 Main Feedwater Pump ML24089A2382024-04-29029 April 2024 Summary of Nuclear Property Insurance IR 05000282/20244012024-04-25025 April 2024 – Security Baseline Inspection Report 05000282/2024401 and 05000306/2024401 ML24100A8042024-04-24024 April 2024 – Alternative Request RR-09 for Safety Injection and Volume Control System Category C Check Valve Inservice Testing ML24114A0882024-04-23023 April 2024 Annual Report of Individual Monitoring for the Prairie Island Nuclear Generating Plant (PINGP) ML24113A1182024-04-12012 April 2024 NRC Letter Re NRC Office of Investigations Report No. 3-2023-004 ML24100A1212024-04-0909 April 2024 Submittal of Revised Pressure and Temperature Limits Report ML24093A2832024-04-0202 April 2024 Nuclear Material Transaction Report L-PI-24-012, Independent Spent Fuel Storage Installation - License Amendment Request: Revise Independent Spent Fuel Storage Installation (ISFSI) License Conditions 23(a), 24(A)(2), and 24(B)(2)2024-04-0202 April 2024 Independent Spent Fuel Storage Installation - License Amendment Request: Revise Independent Spent Fuel Storage Installation (ISFSI) License Conditions 23(a), 24(A)(2), and 24(B)(2) ML24089A2402024-03-29029 March 2024 Guarantee of Payment of Deferred Premiums ML24060A1232024-03-27027 March 2024 To Request 1-RR-5-10 and 2-RR-5-10 Regarding Reactor Pressure Vessel Welds and Nozzle Welds 05000282/LER-2023-001-01, Reactor Trip, Auxiliary Feedwater and Emergency Service Water System Actuation Due to Electrical Transient in DC Control Power Cables2024-03-21021 March 2024 Reactor Trip, Auxiliary Feedwater and Emergency Service Water System Actuation Due to Electrical Transient in DC Control Power Cables ML24262A1512024-03-15015 March 2024 L-PI-24-011 150 Day Letter 2024 PINGP ILT NRC Exam ML24010A0582024-03-0505 March 2024 Amendment No. 12 to Materials License No. Special Nuclear Material-2506 for the Prairie Island Independent Spent Fuel Storage Installation L-PI-24-004, Independent Spent Fuel Storage Installation - Annual Effluent Report, January Through December 20232024-02-29029 February 2024 Independent Spent Fuel Storage Installation - Annual Effluent Report, January Through December 2023 IR 05000282/20230062024-02-28028 February 2024 Annual Assessment Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report 05000282/2023006 and 05000306/2023006) 2024-09-27
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARL-PI-24-044, Application to Revise Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program2024-10-21021 October 2024 Application to Revise Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program L-PI-24-014, License Amendment Request to Revise the Technical Specification Definition of Reactor Trip System (RTS) Response Time and Apply Response Time Testing to RTS Trip Functions with Time Delay Assumption2024-06-0303 June 2024 License Amendment Request to Revise the Technical Specification Definition of Reactor Trip System (RTS) Response Time and Apply Response Time Testing to RTS Trip Functions with Time Delay Assumption ML24155A2222024-05-28028 May 2024 Methodology Evaluation Report for Elimination of Response Time Testing Prairie Island Reactor Trip System Rev. 1 ML23215A1672023-12-15015 December 2023 Acceptance of Requested Licensing Action Amendment Request to Revise Surveillance Requirement 3.8.1.2 Note 3 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 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-23-007, Supplement to Application to Revise Technical Specification Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)2023-03-28028 March 2023 Supplement to Application to Revise Technical Specification Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) L-PI-22-040, Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2022-10-0606 October 2022 Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections 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 L-PI-22-024, Supplement to Application for License Amendment to Implement 24-Month Operating Cycle2022-03-0707 March 2022 Supplement to Application for License Amendment to Implement 24-Month Operating Cycle ML21320A2262021-11-15015 November 2021 License Amendment Request: Standard Emergency Plan and Consolidated Emergency Operations Facility for the Monticello Nuclear Generating Plant and the Prairie Island Nuclear Generating Plant L-PI-21-006, License Amendment Request to Revise Technical Specification 3.3.1, Reactor Trip System (RTS) Instrumentation, to Incorporate Installed Bypass Test Capability for the Power Range RTS Functions2021-10-0202 October 2021 License Amendment Request to Revise Technical Specification 3.3.1, Reactor Trip System (RTS) Instrumentation, to Incorporate Installed Bypass Test Capability for the Power Range RTS Functions L-PI-21-016, Application for License Amendment to Implement 24-Month Operating Cycle2021-08-0606 August 2021 Application for License Amendment to Implement 24-Month Operating Cycle L-PI-21-007, Application to Revise Technical Specifications to Adopt TSTF-471, Eliminate Use of the Term Core Alterations in Actions and Notes2021-04-19019 April 2021 Application to Revise Technical Specifications to Adopt TSTF-471, Eliminate Use of the Term Core Alterations in Actions and Notes L-PI-20-051, Supplement to Application to Revise Technical Specifications to Adopt TSTF-547, Clarification of Rod Position Requirements2020-09-28028 September 2020 Supplement to Application to Revise Technical Specifications to Adopt TSTF-547, Clarification of Rod Position Requirements L-PI-20-004, License Amendment Request to Revise Technical Specifications (TS) to Remove Note I from Limiting Condition for Operating (LCO) 3.4.12 and LCO 3.4.132020-03-30030 March 2020 License Amendment Request to Revise Technical Specifications (TS) to Remove Note I from Limiting Condition for Operating (LCO) 3.4.12 and LCO 3.4.13 ML20058F9432020-02-27027 February 2020 and Prairie Island Nuclear Generating Plant, Units 1 and 2 - License Amendment Request: Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules Revision 4 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-19-031, License Amendment Request: Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2019-12-16016 December 2019 License Amendment Request: Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b 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 L-PI-19-006, Emergency License Amendment Request Regarding One-Time Extension for Technical Specification Completion Time Requirements2019-01-29029 January 2019 Emergency License Amendment Request Regarding One-Time Extension for Technical Specification Completion Time Requirements L-PI-18-064, License Amendment Request (LAR) to Revise Current Licensing Basis, Supplement 12018-12-0404 December 2018 License Amendment Request (LAR) to Revise Current Licensing Basis, Supplement 1 L-PI-18-014, License Amendment Request (LAR) to Revise Current Licensing Basis2018-10-0202 October 2018 License Amendment Request (LAR) to Revise Current Licensing Basis L-PI-18-031, License Amendment Request to Adopt TSTF-439, Revision 2, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an Lco.2018-06-26026 June 2018 License Amendment Request to Adopt TSTF-439, Revision 2, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an Lco. L-PI-18-005, License Amendment Request to Revise License Condition Associated with Implementation of NFPA 8052018-05-18018 May 2018 License Amendment Request to Revise License Condition Associated with Implementation of NFPA 805 ML17090A2012017-03-31031 March 2017 License Amendment Request to Revise Technical Specification for Plant/Unit Staff Qualifications Education and Experience Eligibility Requirements for Licensed Operators ML17094A5762017-03-29029 March 2017 License Amendment Request to Revise Emergency Action Level (EAL) Scheme ML17055C3592017-02-23023 February 2017 License Amendment Request: Revision to Emergency Plan Staff Augmentation Response Times L-PI-16-060, License Amendment Request to Revise Technical Specification 3.8.7 to Remove Non-Conservative Required Action2016-08-31031 August 2016 License Amendment Request to Revise Technical Specification 3.8.7 to Remove Non-Conservative Required Action L-PI-16-020, License Amendment Request Regarding One-Time Extension for Technical Specification Surveillance Requirement 3.8.4.3. DC Sources- Operating.2016-04-0707 April 2016 License Amendment Request Regarding One-Time Extension for Technical Specification Surveillance Requirement 3.8.4.3. DC Sources- Operating. L-PI-16-003, Supplement to License Amendment Request to Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Revision 2, Using the Consolidated Line Item Improvement Process2016-01-25025 January 2016 Supplement to License Amendment Request to Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Revision 2, Using the Consolidated Line Item Improvement Process ML15327A2282015-11-17017 November 2015 License Amendment Request for Spent Fuel Pool Criticality Technical Specification Changes L-PI-15-087, Enclosures 7 & 8: Modeling of Fuel Assemblies Containing Both Ifba and Gadolinia Absorber Rods with Westinghouse Core Design Code Systems and Affidavit2015-10-31031 October 2015 Enclosures 7 & 8: Modeling of Fuel Assemblies Containing Both Ifba and Gadolinia Absorber Rods with Westinghouse Core Design Code Systems and Affidavit 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 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 L-PI-14-072, License Amendment Request (LAR) to Revise the Licensing Basis Analysis for a Waste Gas Decay Tank Rupture2014-08-21021 August 2014 License Amendment Request (LAR) to Revise the Licensing Basis Analysis for a Waste Gas Decay Tank Rupture L-PI-14-037, License Amendment Request (LAR) to Revise Technical Specification (TS) 3.8.1, AC Sources- Operating, Emergency Diesel Generator Voltage and Frequency Limits2014-06-0909 June 2014 License Amendment Request (LAR) to Revise Technical Specification (TS) 3.8.1, AC Sources- Operating, Emergency Diesel Generator Voltage and Frequency Limits ML14126A7272014-05-0505 May 2014 Supplement to License Amendment Request (LAR) for Cyber Security Plan Implementation Date Extension L-PI-13-102, License Amendment Request (LAR) to Revise Staff Augmentation Times in the Prairie Island Nuclear Generating Plant (PINGP) Emergency Plan2013-12-20020 December 2013 License Amendment Request (LAR) to Revise Staff Augmentation Times in the Prairie Island Nuclear Generating Plant (PINGP) Emergency Plan ML13333B6742013-11-27027 November 2013 License Amendment Request (LAR) for Northern States Power Company, Minnesota (NSPM) Cyber Security Plan Implementation Date Extension L-PI-13-076, Supplement to License Amendment Request for Exception to Technical Specification 5.5.14 Testing Requirements Associated with Steam Generator Replacement2013-07-25025 July 2013 Supplement to License Amendment Request for Exception to Technical Specification 5.5.14 Testing Requirements Associated with Steam Generator Replacement L-PI-13-071, Supplement to License Amendment Request (LAR) to Revise Emergency Plan (EP) Emergency Action Levels (Eals): RA 1.2 and Fuel Clad Barrier Loss Criteria2013-07-23023 July 2013 Supplement to License Amendment Request (LAR) to Revise Emergency Plan (EP) Emergency Action Levels (Eals): RA 1.2 and Fuel Clad Barrier Loss Criteria 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). L-PI-13-017, License Amendment Request (LAR) to Revise Technical Specification (TS) 3.5.3, ECCS (Emergency Core Cooling System) - Shutdown2013-02-20020 February 2013 License Amendment Request (LAR) to Revise Technical Specification (TS) 3.5.3, ECCS (Emergency Core Cooling System) - Shutdown L-PI-12-110, License Amendment Request (LAR) to Revise Emergency Plan (EP) Emergency Action Levels (Eals): RA1.2 and Fuel Clad Barrier Loss Criteria2012-12-13013 December 2012 License Amendment Request (LAR) to Revise Emergency Plan (EP) Emergency Action Levels (Eals): RA1.2 and Fuel Clad Barrier Loss Criteria ML12278A4052012-09-28028 September 2012 Prairie Island, Units 1 and 2, License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactors L-PI-12-054, Application to Revise Technical Specifications Associated with Steam Generator Replacement and Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection2012-07-25025 July 2012 Application to Revise Technical Specifications Associated with Steam Generator Replacement and Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection L-PI-12-055, License Amendment Request for Exception to Technical Specification 5.5.14 Testing Requirements Associated with Steam Generator Replacement2012-07-25025 July 2012 License Amendment Request for Exception to Technical Specification 5.5.14 Testing Requirements Associated with Steam Generator Replacement 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-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 2024-06-03
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ATTACHMENT 3 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Letter L-PI-04-014, Supplement to License Amendment Request dated March 25, 2003 Prairie Island Units I and 2 Safety Analysis Transition Program Licensing Report dated January 2004 (Non-Proprietary)
rI C MCa Committed to Nuclear Exc el~
Praide Island Nuclear Generating Plant Operated by Nuclear Management Company, LLC FEB 1 1 2004 L-PI-04-014 10 CFR 50.90 U S Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 PRAIRIE ISLAND NUCLEAR GENERATING PLANT DOCKETS 50-282 AND 50-306 LICENSE Nos. DPR-42 AND DPR-60 SUPPLEMENT TO LICENSE AMENDMENT REQUEST (LAR) DATED MARCH 25, 2003, SAFETY ANALYSES TRANSITION (TAC NOs. MB8128 and MB8129)
By letter dated March 25, 2003, the Nuclear Management Company, LLC (NMC) submitted an LAR titled, "Safety Analyses Transition," which proposes Technical Specification (TS) changes associated with transition to Westinghouse performance of safety analyses for the Prairie Island Nuclear Generating Plant (PINGP).
By letter dated January 14, 2004, NMC provided supplemental information in support of the subject LAR which included an attachment titled, uSafety Analysis Transition Program Licensing Report for the Prairie Island Nuclear Generating Plant," (Licensing Report) dated December 2003. With respect to the Licensing Report the NMC letter dated January 14, 2004 stated:
The enclosed report contains information which is proprietary to Westinghouse Electric Company LLC. Accordingly, Westinghouse requests that this information be withheld from public disclosure. In order not to delay this submittal of information to the Commission in connection with the review of the Licensing Report, Westinghouse will comply with the requirements of 10 CFR 2.790 to provide proprietary and non-proprietary versions together with an affidavit as soon as the proprietary information contained in the submittal have been specifically identified and the proprietary and non-proprietary versions have been prepared. NMC will submit the total required number of copies of the proprietary Attachment 2 Contains Proprietary Information 1717 Wakonade Drive East . Welch, Minnesota 55089-9642 Telephone: 651.388.1121
,- 7 0 a2CA-
USNRC NUCLEAR MANAGEMENT COMPANY, LLC L-PI-04-014 Page 2 and non-proprietary versions of the information and the required affidavit at that time. In the meantime, NMC has provided sufficient copies for the NRC to initiate review. Representatives of the NRC office of the General Counsel have advised Westinghouse that they concur with this procedure.
This letter provides the required documents to meet the requirements of 10 CFR 2.790 for the Licensing Report. NMC submits this supplement in accordance with the provisions of 10 CFR 50.90. is Westinghouse authorization letter CAW-04-1779 with accompanying affidavit, Proprietary Information Notice, and Copyright Notice. As Attachment 2 contains information proprietary to Westinghouse Electric Company LLC, it is supported by an affidavit signed by Westinghouse, the owner of the information. The affidavit sets forth the basis on which the information may be withheld from public disclosure by the Commission and addresses with specificity the considerations listed in paragraph (b)(4) of Section 2.790 of the Commission's regulations. Accordingly it is respectfully requested that the information which is proprietary to Westinghouse be withheld from public disclosure in accordance with 10 CFR Section 2.790 of the Commission's regulations. Correspondence with respect to the copyright or proprietary aspects of the items listed above or the supporting Westinghouse affidavit should reference CAW 1779 and should be addressed to J. A. Gresham, Manager, Regulatory Compliance and Plant Licensing, Westinghouse Electric Company LLC, P.O. Box 355, Pittsburgh, Pennsylvania 15230-0355. provides 5 copies of, "Prairie Island Units 1 and 2 Safety Analysis Transition Program Licensing Report," dated January 2004 (Proprietary). provides 5 copies of, 'Prairie Island Units 1 and 2 Safety Analysis Transition Program Licensing Report," dated January 2004 (Non-Proprietary).
The information provided in this supplement does not impact the conclusions of the Determination of No Significant Hazards Consideration and Environmental Assessment presented in the original March 25, 2003 submittal as supplemented June 16, 2003 and January 14, 2004.
In accordance with 10 CFR 50.91, NMC is notifying the State of Minnesota of this LAR supplement by transmitting a copy of this letter and non-proprietary attachments to the designated State Official.
Attachments 2 Contains Proprietary Information 1717 Wakonade Drive East . Welch, Minnesota 55089-9642 Telephone: 651.388.1121
USNRC NUCLEAR MANAGEMENT COMPANY, LLC L-PI-04-0 14 Page 3 In this letter NMC has not made any new or revised any Nuclear Regulatory Commission commitments. Please address any comments or questions regarding this LAR supplement to Mr. Dale Vincent at 1-651-388-1121.
I declare under penalty of perjury that the foregoing is true and accurate.
Executed on FEB 1 1 2004 Joseph M. Solymossy Site Vice-President, Prairie Island Nuclear Generating Plant CC Regional Administrator, USNRC, Region III Project Manager, Prairie Island Nuclear Generating Plant, USNRC, NRR NRC Resident Inspector- Prairie Island Nuclear Generating Plant Glenn Wilson, State of Minnesota Attachments:
- 1. Westinghouse letter CAW-04-1779 with Affidavit, Proprietary Information Notice, and Copyright Notice
- 2. Prairie Island Units 1 and 2 Safety Analysis Transition Program Licensing Report dated January 2004 (Proprietary)
- 3. Prairie Island Units 1 and 2 Safety Analysis Transition Program Licensing Report dated January 2004 (Non-Proprietary)
I Attachments 2 Contains Proprietary Information I 1717 Wakonade Drive East
- Welch, Minnesota 55089-9642 Telephone: 651.388.1121
ATTACHMENT I PRAIRIE ISLAND NUCLEAR GENERATING PLANT Letter L-PI-04-014, Supplement to License Amendment Request dated March 25, 2003 Westinghouse letter CAW-04-1779 Affidavit CAW-04-1779 Proprietary Information Notice Copyright Notice
Westinghouse Westinghouse Electric Company Nuclear Services P.O.Box355 Pittsburgh, Pennsylvania 15230-0355 USA U.S. Nuclear Regulatory Commission Directtel: (412) 3744643 Document Control Desk Direct fax: (412) 3744011 Washington, DC 20555-0001 e-mail: greshajaewestinghouse.com Ourref: CANV-04-1779 January 23, 2004 APPLICATION FOR WITHHOLDING PROPRIETARY INFORMATION FROM PUBLIC DISCLOSURE
Subject:
"Prairie Island Units 1 and 2 Safety Analysis Transition Program Licensing Report,"
dated January, 2004 (Proprietary)
The proprietary information for which withholding is being requested in the above-referenced report is further identified in Affidavit CAW-04-1779 signed by the owner of the proprietary information, Westinghouse Electric Company LLC. The affidavit, which accompanies this letter, sets forth the basis on which the information may be withheld from public disclosure by the Commission and addresses with specificity the considerations listed in paragraph (b)(4) of 10 CFR Section 2.790 of the Commission's regulations.
Accordingly, this letter authorizes the utilization of the accompanying affidavit by Nuclear Management Company.
Correspondence with respect to the proprietary aspects of the application for withholding or the Westinghouse affidavit should reference this letter, CAW-04-1779, and should be addressed to J. A. Gresham, Manager, Regulatory Compliance and Plant Licensing, Westinghouse Electric Company LLC, P.O. Box 355, Pittsburgh, Pennsylvania 15230-0355.
Very truly yours, J. S. aembush, Acting Manager Regulatory Compliance and Plant Licensing Enclosures cc: D. Holland B. Benney E. Peyton A BNFL Group company
CAW-04-1779 bcc: J. A. Gresharn (ECE 4-7A) IL R. Bastien, IL, IA (Nivelles, Belgium)
C. Brinkman, IL, IA (Westinghouse Electric Co., 12300 Twinbrook Parkway, Suite330, Rockville, MD 20852)
RCPL Administrative Aide (ECE 4-7A) IL, IA (letter and affidavit only)
A BNFL Group company
CAW-04-1 779 AFFIDAVIT COMMONWEALTH OF PENNSYLVANIA:
ss COUNTY OF ALLEGHENY:
Before me, the undersigned authority, personally appeared J. S. Galembush, who, being by me duly sworn according to law, deposes and says that he is authorized to execute this Affidavit on behalf of Westinghouse Electric Company LLC (Westinghouse), and that the averments of fact set forth in this Affidavit are true and correct to the best of his knowledge, information, and belief:
J. S. Galembush, Acting Manager Regulatory Compliance and Plant Licensing Sworn to and subscribed before me this 4,12day of 2004 Notary Public NowSea Sharon L Fbai Notay Rt &
My im BorExes Januaiy 29,2007 Mewtbr. Pemsg4va Assocbimon Of Noaes
2 CAW-04-1779 (1) I am Acting Manager, Regulatory Compliance and Plant Licensing, in Nuclear Services, Westinghouse Electric Company LLC (Westinghouse), and as such, I have been specifically delegated the function of reviewing the proprietary information sought to be withheld from public disclosure in connection with nuclear power plant licensing and rule making proceedings, and am authorized to apply for its withholding on behalf of Westinghouse.
(2) 1 am making this Affidavit in conformance with the provisions of 10 CFR Section 2.790 of the Commission's regulations and in conjunction with the Westinghouse "Application for Withholding" accompanying this Affidavit.
(3) I have personal knowledge of the criteria and procedures utilized by Westinghouse in designating information as a trade secret, privileged or as confidential commercial or financial information.
(4) Pursuant to the provisions of paragraph (b)(4) of Section 2.790 of the Commission's regulations, the following is furnished for consideration by the Commission in determining whether the information sought to be withheld from public disclosure should be withheld.
(i) The information sought to be withheld from public disclosure is owned and has been held in confidence by Westinghouse.
(ii) The information is of a type customarily held in confidence by Westinghouse and not customarily disclosed to the public. Westinghouse has a rational basis for determining the types of information customarily held in confidence by it and, in that connection, utilizes a system to determine when and whether to hold certain types of information in confidence. The application of that system and the substance of that system constitutes Westinghouse policy and provides the rational basis required.
Under that system, information is held in confidence if it falls in one or more of several types, the release of which might result in the loss of an existing or potential competitive advantage, as follows:
(a) The information reveals the distinguishing aspects of a process (or component, structure, tool, method, etc.) where prevention of its use by any of
3 CAW-04-1779 Westinghouse's competitors without license from Westinghouse constitutes a competitive economic advantage over other companies.
(b) It consists of supporting data, including test data, relative to a process (or component, structure, tool, method, etc.), the application of which data secures a competitive economic advantage, e.g., by optimization or improved marketability.
(c) Its use by a competitor would reduce his expenditure of resources or improve his competitive position in the design, manufacture, shipment, installation, assurance of quality, or licensing a similar product.
(d) It reveals cost or price information, production capacities, budget levels, or commercial strategies of Westinghouse, its customers or suppliers.
(e) It reveals aspects of past, present, or future Westinghouse or customer funded development plans and programs of potential commercial value to Westinghouse.
(f) It contains patentable ideas, for which patent protection may be desirable.
There are sound policy reasons behind the Westinghouse system which include the following:
(a) The use of such information by Westinghouse gives Westinghouse a competitive advantage over its competitors. It is, therefore, withheld from disclosure to protect the Westinghouse competitive position.
(b) It is information that is marketable in many ways. The extent to which such information is available to competitors diminishes the Westinghouse ability to sell products and services involving the use of the information.
(c) Use by our competitor would put Westinghouse at a competitive disadvantage by reducing his expenditure of resources at our expense.
4 CAW-04-1779 (d) Each component of proprietary information pertinent to a particular competitive advantage is potentially as valuable as the total competitive advantage. If competitors acquire components of proprietary information, any one component may be the key to the entire puzzle, thereby depriving Westinghouse of a competitive advantage.
(e) Unrestricted disclosure would jeopardize the position of prominence of Westinghouse in the world market, and thereby give a market advantage to the competition of those countries.
(f) The Westinghouse capacity to invest corporate assets in research and development depends upon the success in obtaining and maintaining a competitive advantage.
(iii) The information is being transmitted to the Commission in confidence and, under the provisions of 10 CFR Section 2.790, it is to be received in confidence by the Commission.
(iv) The information sought to be protected is not available in public sources or available information has not been previously employed in the same original manner or method to the best of our knowledge and belief.
(v) The proprietary information sought to be withheld in this submittal is that which is appropriately marked in "Prairie Island Units I and 2 Safety Analysis Transition Program Licensing Report," dated January, 2004 (Proprietary) being transmitted by the Nuclear Management Company letter and Application for Withholding Proprietary Information from Public Disclosure, to the Document Control Desk. The proprietary information as submitted for use by Westinghouse for Prairie Island Units I and 2 is expected to be applicable for other licensee submittals in response to certain NRC requirements for justification of continued safe operation of Prairie Island Units I and 2.
This information is part of that which will enable Westinghouse to:
(a) Determine that applicable safety analysis acceptance criteria have been met.
5 CAW-04-1779 Further this information has substantial commercial value as follows:
(a) Westinghouse plans to sell the use of similar information to its customers for purposes of determining that applicable safety analysis acceptance criteria have been met.
(b) Westinghouse can sell support and defense of the methodology used to perform safety analysis.
(c) The information requested to be withheld reveals the distinguishing aspects of a methodology which was developed by Westinghouse.
Public disclosure of this proprietary information is likely to cause substantial harm to the competitive position of Westinghouse because it would enhance the ability of competitors to provide similar services for commercial power reactors without commensurate expenses. Also, public disclosure of the information would enable others to use the information to meet NRC requirements for licensing documentation without purchasing the right to use the information.
The development of the technology described in part by the information is the result of applying the results of many years of experience in an intensive Westinghouse effort and the expenditure of a considerable sum of money.
In order for competitors of Westinghouse to duplicate this information, similar technical programs would have to be performed and a significant manpower effort, having the requisite talent and experience, would have to be expended.
Further the deponent sayeth not.
PROPRIETARY INFORMATION NOTICE Transmitted herewith are proprietary and/or non-proprietary versions of documents furnished to the NRC in connection with requests for generic and/or plant-specific review and approval.
In order to conform to the requirements of 10 CFR 2.790 of the Commission's regulations concerning the protection of proprietary information so submitted to the NRC, the information which is proprietary in the proprietary versions is contained within brackets, and where the proprietary information has been deleted in the non-proprietary versions, only the brackets remain (the information that was contained within the brackets in the proprietary versions having been deleted). Thejustification for claiming the information so designated as proprietary is indicated in both versions by means of lower case letters (a) through (f) located as a superscript immediately following the brackets enclosing each item of information being identified as proprietary or in the margin opposite such information. These lower case letters refer to the types of information Westinghouse customarily holds in confidence identified in Sections (4)(ii)(a) through (4)(ii)(f) of the affidavit accompanying this transmittal pursuant to 10 CFR 2.790(b)(1).
COPYRIGHT NOTICE The reports transmitted herewith each bear a Westinghouse copyright notice. The NRC is permitted to make the number of copies of the information contained in these reports which are necessary for its internal use in connection with generic and plant-specific reviews and approvals as well as the issuance, denial, amendment, transfer, renewal, modification, suspension, revocation, or violation of a license, permit, order, or regulation subject to the requirements of 10 CFR 2.790 regarding restrictions on public disclosure to the extent such information has been identified as proprietary by Westinghouse, copyright protection notwithstanding. With respect to the non-proprietary versions of these reports, the NRC is permitted to make the number of copies beyond those necessary for its internal use which are necessary in order to have one copy available for public viewing in the appropriate docket files in the public document room in Washington, DC and in local public document rooms as may be required by NRC regulations if the number of copies submitted is insufficient for this purpose. Copies made by the NRC must include the copyright notice in all instances and the proprietary notice if the original was identified as proprietary.