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Category:Letter type:L
MONTHYEARL-PI-24-036, – Preparation and Scheduling of Operator Licensing Examinations2024-06-28028 June 2024 – Preparation and Scheduling of Operator Licensing Examinations 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 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 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) 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 L-PI-24-009, Response to Request for Additional Information Prairie Island Nuclear Generating Plant, Unit 2, Alternative RR-09 Safety Injection System and Volume Control System Category C Check Valve Quarterly Testing2024-02-13013 February 2024 Response to Request for Additional Information Prairie Island Nuclear Generating Plant, Unit 2, Alternative RR-09 Safety Injection System and Volume Control System Category C Check Valve Quarterly Testing 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 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 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-23-023, Baffle Former Bolts Alternate Aging Management Strategy2023-09-11011 September 2023 Baffle Former Bolts Alternate Aging Management Strategy 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 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 L-PI-23-010, Annual Report of Individual Monitoring2023-04-27027 April 2023 Annual Report of Individual Monitoring 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-23-005, CFR 50.55a Requests Nos. 1-RR-5-15 and 2-RR-5-15, Proposed Use of Subsequent ASME Code Edition and Addenda in Accordance with 10 CFR 50.55a(g)(4)(iv)2023-03-0303 March 2023 CFR 50.55a Requests Nos. 1-RR-5-15 and 2-RR-5-15, Proposed Use of Subsequent ASME Code Edition and Addenda in Accordance with 10 CFR 50.55a(g)(4)(iv) L-PI-23-001, Day Steam Generator Tube Inspection Report2023-01-30030 January 2023 Day Steam Generator Tube Inspection Report L-PI-22-047, Resubmittal of Prairie Island Nuclear Generating Plant (PINGP) 2018 Unit 1 180-Day Steam Generator Tube Inspection Report2022-12-21021 December 2022 Resubmittal of Prairie Island Nuclear Generating Plant (PINGP) 2018 Unit 1 180-Day Steam Generator Tube Inspection Report L-PI-22-020, Application to Revise Technical Specification Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)2022-12-0202 December 2022 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-22-037, Updated Approach for Prairie Island Unit 1 and Unit 2 Baffle Former Bolts2022-09-20020 September 2022 Updated Approach for Prairie Island Unit 1 and Unit 2 Baffle Former Bolts L-PI-22-032, CFR 50.46 LOCA Annual Report2022-06-16016 June 2022 CFR 50.46 LOCA Annual Report L-PI-22-033, Response to Request for Additional Information Prairie Island Nuclear Generating Plant, Units 1 and 2, Amendment to Adopt 24-Month Operating Cycles2022-06-10010 June 2022 Response to Request for Additional Information Prairie Island Nuclear Generating Plant, Units 1 and 2, Amendment to Adopt 24-Month Operating Cycles 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 L-PI-21-047, Response to Request for Additional Information 24-Month Cycle Amendment Prairie Island Nuclear Generating Plant, Units 1 and 22021-12-0707 December 2021 Response to Request for Additional Information 24-Month Cycle Amendment Prairie Island Nuclear Generating Plant, Units 1 and 2 L-PI-21-045, Response to Request for Additional Information Cooling Water System License Amendment Request2021-11-0404 November 2021 Response to Request for Additional Information Cooling Water System License Amendment Request 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 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-21-032, Response to Request for Additional Information Amendment Request to Adopt TSTF-471 and 571-T for Prairie Island2021-09-30030 September 2021 Response to Request for Additional Information Amendment Request to Adopt TSTF-471 and 571-T for Prairie Island 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-21-027, 2020 10 CFR 50.46 LOCA Annual Report2021-06-28028 June 2021 2020 10 CFR 50.46 LOCA Annual Report L-PI-21-023, Independent Spent Fuel Storage Installation - 2020 Annual Radiological Environmental Monitoring Program Report2021-05-14014 May 2021 Independent Spent Fuel Storage Installation - 2020 Annual Radiological Environmental Monitoring Program Report 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-20-050, Request for a One-Time Exemption from 10 CFR 50, Appendix E, Biennial Emergency Preparedness Exercise Requirements, Due to COVID-19 Pandemic2020-10-0707 October 2020 Request for a One-Time Exemption from 10 CFR 50, Appendix E, Biennial Emergency Preparedness Exercise Requirements, Due to COVID-19 Pandemic 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-20-026, Response to Request for Additional Information: License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiativ2020-09-0101 September 2020 Response to Request for Additional Information: License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4 L-PI-20-035, = Request for Revision to Reactor Vessel Material Surveillance Capsule Removal Schedule2020-07-28028 July 2020 = Request for Revision to Reactor Vessel Material Surveillance Capsule Removal Schedule L-PI-20-023, Independent Spent Fuel Storage Installation, Response to Request for Additional Information: License Amendment Request to Expand the Storage Capacity of the Independent Spent Fuel Storage Installation (ISFSI)2020-06-10010 June 2020 Independent Spent Fuel Storage Installation, Response to Request for Additional Information: License Amendment Request to Expand the Storage Capacity of the Independent Spent Fuel Storage Installation (ISFSI) L-PI-20-014, Supplement to License Amendment Request: Expand the Storage Capacity of the Independent Spent Fuel Storage Installation (ISFSI2020-04-29029 April 2020 Supplement to License Amendment Request: Expand the Storage Capacity of the Independent Spent Fuel Storage Installation (ISFSI 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 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-19-031, 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-19-038, Submittal of Revised Pressure and Temperature Limits Report2019-09-19019 September 2019 Submittal of Revised Pressure and Temperature Limits Report L-PI-19-037, Response to Request for Additional Information: 10 CFR 50.55a Requests Nos. 1-RR-5-10 and 2-RR-5-10, Proposed Alternative to Reactor Vessel Inservice Inspection (ISI) Intervals2019-09-16016 September 2019 Response to Request for Additional Information: 10 CFR 50.55a Requests Nos. 1-RR-5-10 and 2-RR-5-10, Proposed Alternative to Reactor Vessel Inservice Inspection (ISI) Intervals L-PI-19-025, Request to Approve Site-Specific Probabilistic Risk Assessment (PRA) Model for Flowserve N-Seal Abeyance Seal and Dynamic Testing for the Prairie Island Nuclear Generating Plant (PINGP)2019-08-27027 August 2019 Request to Approve Site-Specific Probabilistic Risk Assessment (PRA) Model for Flowserve N-Seal Abeyance Seal and Dynamic Testing for the Prairie Island Nuclear Generating Plant (PINGP) 2024-06-05
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NMC> Commrtted to Nuclear Excellence Prairie lsland Nuclear Generating Plant Operated by Nuclear Management Company, LLC May 16,2008 L-PI-08-043 10 CFR Part 54 U S Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Prairie lsland Nuclear Generating Plant Units 1 and 2 Dockets 50-282 and 50-306 License Nos. DPR-42 and DPR-60 Su~plemental Information Regarding Application for Renewed Operatinq Licenses By letter dated April 11, 2008, the Nuclear Management Company, LLC (NMC) submitted an Application for Renewed Operating Licenses (LRA) for the Prairie lsland Nuclear Generating Plant (PINGP) Units 1 and 2. This letter supplements the LRA to incorporate within the scope of License Renewal, additional components related to Station Blackout recovery.
In a telephone conference call on May 15, 2008, the NRC staff communicated a concern with the License Renewal scoping boundary defined in the LRA for equipment in the Prairie lsland Substation. The boundary defined in the LRA is the jurisdictional boundary between plant equipment and non-plant transmission system equipment. The staff indicated that the scoping boundary would be required to encompass certain non- plant transmission system busses and breakers to comply with draft License Renewal Interim Staff Guidance LR-ISG-2008-01, "Staff Guidance Regarding the Station Blackout Rule (10 CFR 50.63) Associated With License Renewal Applications," published in the Federal Register for public comment on March 12, 2008 (73FR13258). Enclosure 1 provides the LRA changes necessary to comply with the staff position in draft LR-ISG-2008-01. If there are any questions or if additional information is needed, please contact Mr. Eugene Eckholt, License Renewal Project Manager.
Summarv of Commitments This letter contains no new commitments or changes to existing commitments.
1717 Wakonade Drive East Welch, Minnesota 55089-9642 Telephone:
651.388.1 121 Document Control Desk Page 2 I declare under penalty of perjury that the foregoing is true and correct. Executed on May 16,2008. Michael D. Wadley Site Vice President, Prairie and Nuclear Generating Plant Units 1 and 2 Nuclear Management Company, LLC Enclosure (1 ) cc: President of the Prairie Island Indian Community Tribal Council Minnesota Department of Commerce Administrator, Region Ill, USNRC License Renewal Project Manager, Prairie Island, USNRC Operating Reactor Licensing Project Manager, Prairie Island, USNRC Resident Inspector, Prairie Island, USNRC ENCLOSURE 1 LICENSE RENEWAL APPLICATION (LRA) CHANGES TO EXPAND THE SCOPING BOUNDARY FOR STATION BLACKOUT RECOVERY The Prairie Island Nuclear Generating Plant (PINGP) Application for Renewed Operating Licenses is hereby revised as follows: LRA Section 2.1 .I .3 In LRA Section 2.1 .I .3, Interim Staff Guidance (ISG) Discussion, replace the existing item 7 with new item 7, to read as follows: "7. Draft LR-ISG-2008-01, "Staff Guidance Regarding the Station Blackout Rule (10 CFR 50.63) Associated with License Renewal Applications" On March 12, 2008, the NRC published draft LR-ISG-2008-01 in the Federal Register for public comment. This ISG is intended to provide additional clarification to the NRC staff position on License Renewal scoping requirements regarding the offsite power system for SBO recovery. Guidance was previously provided in LR- ISG-02 which was cancelled after incorporation into NUREG-1 800 Revision 1, Section 2.5.2.1 .I. The examples referenced in the draft ISG illustrate SBO scoping boundaries which incorporate portions of the transmission system high voltage substations in addition to plant equipment. Based on the examples in this draft ISG, the Prairie Island Substation scoping boundaries have been expanded to include portions of the transmission system in scope of License Renewal. The transmission system components were brought into scope for License Renewal aging management purposes only, and are not part of the CLB description of SBO recovery paths under 10 CFR 50.63. The substation scoping boundaries and associated aging management review discussions provided in Sections 2 and 3 of this LRA reflect these expanded boundaries." LRA Section 2.5 At the end of LRA Section 2.5, Scoping and Screening Results: Electrical and Instrumentation and Controls Systems, after the sentence, "Each of these power sources can power both safeguards busses for both Units using tie breakers," add new paragraphs to read as follows: "As discussed in LRA Section 2.1 .I .3, the scoping boundaries in the Prairie Island Substation have been expanded beyond the plant system equipment to include portions of the transmission system that are controlled and maintained by the transmission system operator. Transmission system components have been brought into scope for License Renewal aging management purposes only, and are not part of the CLB description of SBO recovery paths under 10 CFR 50.63.
ENCLOSURE 1 LICENSE RENEWAL APPLICATION (LRA) CHANGES TO EXPAND THE SCOPING BOUNDARY FOR STATION BLACKOUT RECOVERY The scoping boundaries for the transmission system portion of the Prairie Island Substation begin at the SBO recovery path boundaries described above, and extend outward to the following breakers:
345 kV Breakers 8H7,8H9, 8H13,8H15,8HI6,8H18 161 kV Breaker 6H5 The major substation components within the expanded boundaries brought into scope of License Renewal include the listed breakers and the following:
345 kV Bus 1 345 kV Bus 2 161 kV Bus 1 including Breaker 6H2 No. 10 Transformer and associated 13.8 kV components" LRA Section 2.5.10 Delete the existing discussion in Section 2.5.10, Transmission Conductors and Connections, in its entirety, and insert the following new paragraph:
"345kV and 161 kV transmission conductors and connections that feed in-scope PlNGP offsite power supply paths are in scope of License Renewal due to supporting the SBO recovery path. This electrical commodity requires an AMR." LRA Appendix A, Section A2.0 To the end of the existing Section A2.0, Summary Descriptions of Programs that Manage the Effects of Aging, add the following new paragraph: "Certain programs are being applied to non-plant transmission system equipment in the Prairie Island Substation which is controlled and maintained by the transmission system operator. Program activities for non-plant equipment are performed for aging management purposes only. For the affected substation equipment, PlNGP will assure that the program inspections are performed using procedures subject to plant administrative controls. Degraded conditions identified by those inspections will be entered into the plant Corrective Action Program. Actions required to resolve inspection findings will be referred to the transmission system operator to accomplish, and will be tracked to completion and trended within the plant Corrective Action Program."
ENCLOSURE I LICENSE RENEWAL APPLICATION (LRA) CHANGES TO EXPAND THE SCOPING BOUNDARY FOR STATION BLACKOUT RECOVERY LRA Appendix A, Section A2.11 To the end of the existing program description in Section A2.11, Electrical Cable Connections Not Subject to 10 CFR 50.49 Environmental Qualification Requirements Program, add the following sentence: "For aging management purposes only, this program is also being applied to certain non-plant transmission system equipment in the Prairie lsland Substation." LRA Appendix A, Section A2.38 To the end of the existing program description in Section A2.38, Structures Monitoring Program, add the following sentence: "For aging management purposes only, this program is also being applied to certain non-plant transmission system equipment in the Prairie lsland Substation." LRA Appendix B, Section 81.3 In LRA Section B1.3, Quality Assurance Program and Administrative Controls, after the second full existing paragraph, insert the following new paragraph: "Certain AMPS are being applied to non-plant transmission system equipment in the Prairie lsland Substation which is controlled and maintained by the transmission system operator. The elements of corrective actions, confirmation process and administrative controls described in this section are also applicable to these aging management activities for non-plant equipment, and will be addressed, as applicable, in interface agreements between PlNGP and the transmission system operator." LRA Appendix 6, Section 82.1 .I 1 To the end of the program description in Section B2.1 .I 1, Electrical Cable Connections Not Subject to 10 CFR 50.49 Environmental Qualification Requirements Program, add the following new paragraph: "In response to draft LR-ISG-2008-01 discussed in LRA Section 2.1 .I .3, this program is being applied to certain non-plant transmission system equipment in the Prairie lsland Substation which is controlled and maintained by the transmission system operator."
ENCLOSURE I LICENSE RENEWAL APPLICATION (LRA) CHANGES TO EXPAND THE SCOPING BOUNDARY FOR STATION BLACKOUT RECOVERY LRA Appendix B, Section B2.1.38 To the end of the program description in Section B2.1.38, Structures Monitoring Program, add the following new paragraph: "In response to draft LR-ISG-2008-01 discussed in LRA Section 2.1 .I .3, this program is being applied to certain non-plant transmission system equipment in the Prairie Island Substation which is controlled and maintained by the transmission system operator."