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| | issue date = 10/17/2013 | | | issue date = 10/17/2013 |
| | title = NFPA 805 License Amendment Request- Milestone Schedule for Submittal of Supplement | | | title = NFPA 805 License Amendment Request- Milestone Schedule for Submittal of Supplement |
| | author name = Lynch J E | | | author name = Lynch J |
| | author affiliation = Northern States Power Co, Xcel Energy | | | author affiliation = Northern States Power Co, Xcel Energy |
| | addressee name = | | | addressee name = |
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| {{#Wiki_filter:Xcel Energy Prairie Island Nuclear Generating Plant 1717 Wakonade Drive East Welch, MN 55089 October 17,2013 L-PI-13-093 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Prairie Island Nuclear Generating Plant Units 1 and 2 Dockets 50-282 and 50-306 Renewed License Nos. DPR-42 and DPR-60 NFPA 805 License Amendment Request-Milestone Schedule for Submittal of Supplement (TAC Nos. ME9734 and ME9735) | | {{#Wiki_filter:Xcel Energy Prairie Island Nuclear Generating Plant 1717 Wakonade Drive East Welch, MN 55089 October 17,2013 L-PI-13-093 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Prairie Island Nuclear Generating Plant Units 1 and 2 Dockets 50-282 and 50-306 Renewed License Nos. DPR-42 and DPR-60 NFPA 805 License Amendment Request- Milestone Schedule for Submittal of Supplement (TAC Nos. ME9734 and ME9735) |
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| ==References:== | | ==References:== |
| : 1. NSPM letter, J.P. Sorensen to NRC Document Control Desk, "License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactors," L-PI-12-089, dated September 28, 2012 (ADAMS Accession No. ML 12278A405). | | : 1. NSPM letter, J.P. Sorensen to NRC Document Control Desk, "License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactors," L-PI-12-089, dated September 28, 2012 (ADAMS Accession No. ML12278A405). |
| : 2. NSPM letter, J.E. Lynch to NRC Document Control Desk, "Commitment to Submit a Supplement to the PINGP NFPA 805 License Amendment Request (TAC Nos. ME9734 and ME9735)," L-PI-13-044, dated May 3, 2013 (ADAMS Accession No. ML13126A115). | | : 2. NSPM letter, J.E. Lynch to NRC Document Control Desk, "Commitment to Submit a Supplement to the PINGP NFPA 805 License Amendment Request (TAC Nos. ME9734 and ME9735)," L-PI-13-044, dated May 3, 2013 (ADAMS Accession No. ML13126A115). |
| : 3. NRC letter, T.J. Wengert to J.E. Lynch, "Prairie Island Nuclear Generating Plant, Units 1 and 2 -Status of Review of National Fire Protection Association Standard 805 Application (TAC Nos. ME9734 and ME9735)," dated October 9, 2013 (ADAMS Accession No. ML 13282A538). | | : 3. NRC letter, T.J. Wengert to J.E. Lynch, "Prairie Island Nuclear Generating Plant, Units 1 and 2 - Status of Review of National Fire Protection Association Standard 805 Application (TAC Nos. |
| In Reference 1, Northern States Power Company, a Minnesota Corporation (NSPM), doing business as Xcel Energy, submitted a License Amendment Request (LAR) to the Nuclear Regulatory Commission (NRC), to adopt National Fire Protection Association Standard 805 (NFPA 805) as the licensing basis standard for the fire protection program at the Prairie Island Nuclear Generating Plant (PINGP). In Reference 2, NSPM explained that the PINGP Fire Probabilistic Risk Assessment (PRA) was being revised, and committed to provide the results in a supplement to the LAR by May 1, 2014. | | ME9734 and ME9735)," dated October 9, 2013 (ADAMS Accession No. ML13282A538). |
| Document Control Desk Page2 During subsequent discussions with the NRC Staff on October 8, 2013, and in a letter dated October 9, 2013, the NRC requested that NSPM provide a schedule and interim milestones for submitting the LAR supplement. | | In Reference 1, Northern States Power Company, a Minnesota Corporation (NSPM), |
| The enclosure to this letter provides the requested milestones with scheduled completion dates. This letter is submitted in accordance with 10 CFR 50.90. The information provided in this letter does not impact the conclusions of the No Significant Hazards Evaluation or Environmental Considerations Evaluation presented in the Reference 1 submittal. | | doing business as Xcel Energy, submitted a License Amendment Request (LAR) to the Nuclear Regulatory Commission (NRC), to adopt National Fire Protection Association Standard 805 (NFPA 805) as the licensing basis standard for the fire protection program at the Prairie Island Nuclear Generating Plant (PINGP). In Reference 2, NSPM explained that the PINGP Fire Probabilistic Risk Assessment (PRA) was being revised, and committed to provide the results in a supplement to the LAR by May 1, 2014. |
| | |
| | Document Control Desk Page2 During subsequent discussions with the NRC Staff on October 8, 2013, and in a letter dated October 9, 2013, the NRC requested that NSPM provide a schedule and interim milestones for submitting the LAR supplement. The enclosure to this letter provides the requested milestones with scheduled completion dates. |
| | This letter is submitted in accordance with 10 CFR 50.90. The information provided in this letter does not impact the conclusions of the No Significant Hazards Evaluation or Environmental Considerations Evaluation presented in the Reference 1 submittal. |
| In accordance with 10 CFR 50.91, NSPM is notifying the State of Minnesota by transmitting a copy of this letter to the designated State Official. | | In accordance with 10 CFR 50.91, NSPM is notifying the State of Minnesota by transmitting a copy of this letter to the designated State Official. |
| If there are any questions or if additional information is needed, please contact Gene Eckholt at 651-267-1742. | | If there are any questions or if additional information is needed, please contact Gene Eckholt at 651-267-1742. |
| Summary of Commitments This letter contains no new commitments and no revisions to existing commitments. | | Summary of Commitments This letter contains no new commitments and no revisions to existing commitments. |
| I declare under penalty of perjury that the foregoing is true and correct. Executed on I tJ /;7/.Jo;J Site Vice President, Prairie Island Nuclear Generating Plant Northern States Power Company-Minnesota Enclosure cc: Administrator, Region Ill, USNRC NRR Project Manager, PINGP, USNRC Resident Inspector, PINGP, USNRC Minnesota Department of Commerce L-PI-13-093 ENCLOSURE Schedule for May 1, 2014 Supplement To NFPA 805 License Amendment Request This enclosure provides interim scheduling milestones for submittal of the May 1, 2014 supplement to the NFPA 805 License Amendment Request for the Prairie Island Nuclear Generating Plant. The Northern States Power Company, a Minnesota corporation (NSPM) doing business as Xcel Energy, committed to provide this supplement in a letter dated May 3, 2013 (ADAMS Accession No. ML 13126A115). | | I declare under penalty of perjury that the foregoing is true and correct. |
| The milestone tasks and completion dates that NSPM established to support this submittal are as follows: Interim Milestone Identify Revisions to Variances from Deterministic Requirements Revision to Fire Probabilistic Risk Model Completion Date November 25, 2013 December 12, 2013 LAR Attachments Complete February 21, 2014 A (Fire Protection Program and Design Elements) | | Executed on I tJ /;7/.Jo;J |
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| | Site Vice President, Prairie Island Nuclear Generating Plant Northern States Power Company- Minnesota Enclosure cc: Administrator, Region Ill, USNRC NRR Project Manager, PINGP, USNRC Resident Inspector, PINGP, USNRC Minnesota Department of Commerce |
| | |
| | L-PI-13-093 ENCLOSURE Schedule for May 1, 2014 Supplement To NFPA 805 License Amendment Request This enclosure provides interim scheduling milestones for submittal of the May 1, 2014 supplement to the NFPA 805 License Amendment Request for the Prairie Island Nuclear Generating Plant. The Northern States Power Company, a Minnesota corporation (NSPM) doing business as Xcel Energy, committed to provide this supplement in a letter dated May 3, 2013 (ADAMS Accession No. ML13126A115). The milestone tasks and completion dates that NSPM established to support this submittal are as follows: |
| | Interim Milestone Completion Date Identify Revisions to Variances from Deterministic November 25, 2013 Requirements Revision to Fire Probabilistic Risk Model December 12, 2013 LAR Attachments Complete February 21, 2014 A (Fire Protection Program and Design Elements) |
| B (Nuclear Safety Capability Assessment Methodology) | | B (Nuclear Safety Capability Assessment Methodology) |
| D (Non-Power Operational Modes) H (Frequently Asked Questions) | | D (Non-Power Operational Modes) |
| U (Internal Events PRA Quality) Fire Risk Evaluations (FREs) Complete LAR Attachments Complete (FRE, PRA-related) | | H (Frequently Asked Questions) |
| C (Fire Area Transition) | | U (Internal Events PRA Quality) |
| | Fire Risk Evaluations (FREs) Complete March 7, 2014 LAR Attachments Complete (FRE, PRA-related) April 17, 2014 C (Fire Area Transition) |
| F (Multiple Spurious Operations) | | F (Multiple Spurious Operations) |
| G (Recovery Actions) S (Implementation Items) V (Fire PRA Quality) W (Risk Insights) | | G (Recovery Actions) |
| Plant Operating Review Committee Review Submit to NRC March 7, 2014 April 17, 2014 April 25, 2014 May 1, 2014}} | | S (Implementation Items) |
| | V (Fire PRA Quality) |
| | W (Risk Insights) |
| | Plant Operating Review Committee Review April 25, 2014 Submit to NRC May 1, 2014}} |
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MONTHYEARL-PI-12-102, Supplement to License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactors - Submittal of Lnternal Flooding Peer Review Final Results and Revised Total Plant Risk Values2012-11-0808 November 2012 Supplement to License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactors - Submittal of Lnternal Flooding Peer Review Final Results and Revised Total Plant Risk Values Project stage: Supplement ML12335A1832012-11-29029 November 2012 11/29/12 E-mail, Acceptance Review Questions Regarding NFPA 805 License Amendment Request Project stage: Acceptance Review L-PI-12-117, Supplement to License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactors - Response to Acceptance Review Questions2012-12-18018 December 2012 Supplement to License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactors - Response to Acceptance Review Questions Project stage: Supplement L-PI-13-044, Commitment to Submit a Supplement to the PINGP NFPA 805 License Amendment Request2013-05-0303 May 2013 Commitment to Submit a Supplement to the PINGP NFPA 805 License Amendment Request Project stage: Supplement ML13282A5382013-10-0909 October 2013 Status of Review of National Fire Protection Association Standard 805 Application Project stage: Approval L-PI-13-093, NFPA 805 License Amendment Request- Milestone Schedule for Submittal of Supplement2013-10-17017 October 2013 NFPA 805 License Amendment Request- Milestone Schedule for Submittal of Supplement Project stage: Supplement ML15062A1502015-03-0303 March 2015 NRR E-mail Capture - Prairie Island Nuclear Plant, Units 1 and 2 - NFPA 805 Pre-Audit Draft Requests for Additional Information Project stage: Draft RAI ML15089A1572015-03-30030 March 2015 NRR E-mail Capture - Prairie Island Nuclear Generating Plant, Units 1 and 2 - NFPA 805 Requests for Additional Information and Response Timeline Project stage: RAI L-PI-15-041, License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactors - Response to Request for Additional Information2015-05-28028 May 2015 License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactors - Response to Request for Additional Information Project stage: Response to RAI L-PI-15-052, License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactors - Response to Request for Additional Information - 90-Day Responses2015-06-19019 June 2015 License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactors - Response to Request for Additional Information - 90-Day Responses Project stage: Response to RAI ML15243A4092015-08-28028 August 2015 NRR E-mail Capture - Prairie Island Nuclear Generating Plant - Final Requests for Additional Information (Second Round) from Apla LAR to Adopt NFPA 805 Project stage: RAI ML15243A4102015-08-28028 August 2015 NRR E-mail Capture - Prairie Island Nuclear Generating Plant - Final Requests for Additional Information (Fire Modeling - Second Round) LAR to Adopt NFPA 805 Project stage: RAI L-PI-15-059, License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Information (PRA-Second Round)2015-10-22022 October 2015 License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Information (PRA-Second Round) Project stage: Request L-PI-16-004, License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactors- Response to Request for Additional Information2016-01-20020 January 2016 License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactors- Response to Request for Additional Information Project stage: Response to RAI L-PI-16-005, License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactors - Response to Request for Additional Information2016-05-24024 May 2016 License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactors - Response to Request for Additional Information Project stage: Response to RAI 2015-10-22
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Category:Letter type:L
MONTHYEARL-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) L-PI-19-029, Supplement to Response to Request for Additional Information: Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components For...2019-08-0505 August 2019 Supplement to Response to Request for Additional Information: Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components For... L-PI-19-002, 10 CFR 50.55a Requests Nos. 1-RR-5-10 and 2-RR-5-10, Proposed Alternative to Reactor Vessel Inservice Inspection (ISI) Intervals for Prairie Island, Unit 1 and Unit 22019-06-13013 June 2019 10 CFR 50.55a Requests Nos. 1-RR-5-10 and 2-RR-5-10, Proposed Alternative to Reactor Vessel Inservice Inspection (ISI) Intervals for Prairie Island, Unit 1 and Unit 2 L-PI-19-014, Response to Request for Additional Information: Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2019-04-29029 April 2019 Response to Request for Additional Information: Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors L-PI-19-003, Request for Revision to Reactor Vessel Material Surveillance Capsule Removal Schedule for Prairie Island Nuclear Generating Plant (PINGP)2019-02-0404 February 2019 Request for Revision to Reactor Vessel Material Surveillance Capsule Removal Schedule for Prairie Island Nuclear Generating Plant (PINGP) 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-19-005, Online Reference Portal for NRC Review of License Amendment Request to Implement 10 CFR 50.692019-01-15015 January 2019 Online Reference Portal for NRC Review of License Amendment Request to Implement 10 CFR 50.69 L-PI-18-063, Response to Request for Additional Information: Revise License Condition Associated with Implementation of NFPA 8052018-12-0606 December 2018 Response to Request for Additional Information: Revise License Condition Associated with Implementation of NFPA 805 2024-01-02
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Xcel Energy Prairie Island Nuclear Generating Plant 1717 Wakonade Drive East Welch, MN 55089 October 17,2013 L-PI-13-093 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Prairie Island Nuclear Generating Plant Units 1 and 2 Dockets 50-282 and 50-306 Renewed License Nos. DPR-42 and DPR-60 NFPA 805 License Amendment Request- Milestone Schedule for Submittal of Supplement (TAC Nos. ME9734 and ME9735)
References:
- 1. NSPM letter, J.P. Sorensen to NRC Document Control Desk, "License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactors," L-PI-12-089, dated September 28, 2012 (ADAMS Accession No. ML12278A405).
- 2. NSPM letter, J.E. Lynch to NRC Document Control Desk, "Commitment to Submit a Supplement to the PINGP NFPA 805 License Amendment Request (TAC Nos. ME9734 and ME9735)," L-PI-13-044, dated May 3, 2013 (ADAMS Accession No. ML13126A115).
- 3. NRC letter, T.J. Wengert to J.E. Lynch, "Prairie Island Nuclear Generating Plant, Units 1 and 2 - Status of Review of National Fire Protection Association Standard 805 Application (TAC Nos.
ME9734 and ME9735)," dated October 9, 2013 (ADAMS Accession No. ML13282A538).
In Reference 1, Northern States Power Company, a Minnesota Corporation (NSPM),
doing business as Xcel Energy, submitted a License Amendment Request (LAR) to the Nuclear Regulatory Commission (NRC), to adopt National Fire Protection Association Standard 805 (NFPA 805) as the licensing basis standard for the fire protection program at the Prairie Island Nuclear Generating Plant (PINGP). In Reference 2, NSPM explained that the PINGP Fire Probabilistic Risk Assessment (PRA) was being revised, and committed to provide the results in a supplement to the LAR by May 1, 2014.
Document Control Desk Page2 During subsequent discussions with the NRC Staff on October 8, 2013, and in a letter dated October 9, 2013, the NRC requested that NSPM provide a schedule and interim milestones for submitting the LAR supplement. The enclosure to this letter provides the requested milestones with scheduled completion dates.
This letter is submitted in accordance with 10 CFR 50.90. The information provided in this letter does not impact the conclusions of the No Significant Hazards Evaluation or Environmental Considerations Evaluation presented in the Reference 1 submittal.
In accordance with 10 CFR 50.91, NSPM is notifying the State of Minnesota by transmitting a copy of this letter to the designated State Official.
If there are any questions or if additional information is needed, please contact Gene Eckholt at 651-267-1742.
Summary of Commitments This letter contains no new commitments and no revisions to existing commitments.
I declare under penalty of perjury that the foregoing is true and correct.
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Site Vice President, Prairie Island Nuclear Generating Plant Northern States Power Company- Minnesota Enclosure cc: Administrator, Region Ill, USNRC NRR Project Manager, PINGP, USNRC Resident Inspector, PINGP, USNRC Minnesota Department of Commerce
L-PI-13-093 ENCLOSURE Schedule for May 1, 2014 Supplement To NFPA 805 License Amendment Request This enclosure provides interim scheduling milestones for submittal of the May 1, 2014 supplement to the NFPA 805 License Amendment Request for the Prairie Island Nuclear Generating Plant. The Northern States Power Company, a Minnesota corporation (NSPM) doing business as Xcel Energy, committed to provide this supplement in a letter dated May 3, 2013 (ADAMS Accession No. ML13126A115). The milestone tasks and completion dates that NSPM established to support this submittal are as follows:
Interim Milestone Completion Date Identify Revisions to Variances from Deterministic November 25, 2013 Requirements Revision to Fire Probabilistic Risk Model December 12, 2013 LAR Attachments Complete February 21, 2014 A (Fire Protection Program and Design Elements)
B (Nuclear Safety Capability Assessment Methodology)
D (Non-Power Operational Modes)
H (Frequently Asked Questions)
U (Internal Events PRA Quality)
Fire Risk Evaluations (FREs) Complete March 7, 2014 LAR Attachments Complete (FRE, PRA-related) April 17, 2014 C (Fire Area Transition)
F (Multiple Spurious Operations)
G (Recovery Actions)
S (Implementation Items)
V (Fire PRA Quality)
W (Risk Insights)
Plant Operating Review Committee Review April 25, 2014 Submit to NRC May 1, 2014