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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
MONTHYEARIR 05000282/20230042024-02-0101 February 2024 Integrated Inspection Report 05000282/2023004 and 05000306/2023004 ML23356A1232024-01-29029 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting) ML24024A0722024-01-24024 January 2024 Independent Spent Fuel Storage Installation, Onticello, Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML24017A0182024-01-19019 January 2024 Confirmation of Initial License Examination ML23356A0032024-01-17017 January 2024 Issuance of Amendments Revise Technical Specification 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) L-PI-23-034, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.7.8, Cooling Water (Cl) System,2024-01-0202 January 2024 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.7.8, Cooling Water (Cl) System, L-PI-23-035, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report2023-12-20020 December 2023 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report IR 07200010/20234012023-12-20020 December 2023 Independent Spent Fuel Storage Installation Security Inspection Report 07200010/2023401 ML23349A0572023-12-15015 December 2023 and Independent Spent Fuel Storage Installation, Revision to Correspondence Service List for Northern States Power - Minnesota ML23215A1672023-12-15015 December 2023 Acceptance of Requested Licensing Action Amendment Request to Revise Surveillance Requirement 3.8.1.2 Note 3 IR 05000282/20234012023-12-13013 December 2023 Security Baseline Inspection Report 05000282/2023401 and 05000306/2023401 L-PI-23-033, Supplement to License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 32023-12-0505 December 2023 Supplement to License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 3 ML23304A1632023-11-15015 November 2023 Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment Request to Revise SR 3.8.1.2 Note 3 ML23319A3182023-11-15015 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000282/20230032023-11-0808 November 2023 Integrated Inspection Report 05000282/2023003 and 05000306/2023003 ML23311A3572023-11-0707 November 2023 Core Operating Limits Report (COLR) for Prairie Island Nuclear Generating Plant (PINGP) Unit 2. Cycle 33. Revision 0 ML23285A3062023-10-12012 October 2023 Implementation of the Fleet Standard Emergency Plan for the Monticello Nuclear Generating Plant and the Prairie Island Nuclear Generating Plant ML23270B9022023-09-29029 September 2023 Review of Reactor Vessel Material Surveillance Program Capsule N Technical Report L-PI-23-025, License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 32023-09-28028 September 2023 License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 3 ML23265A2532023-09-26026 September 2023 Review of Reactor Vessel Material Surveillance Program Capsule N Technical Report ML23262B0372023-09-19019 September 2023 Response to NRC Request for Additional Information Regarding the 2023 Monticello and Prairie Island Plant Decommissioning Funding Status Reports ML23256A1682023-09-13013 September 2023 Independent Spent Fuel Storage Installation and Monticello Nuclear Generating Plant - Voluntary Security Clearance Program 2023 Insider Threat Program Self-Inspection L-PI-23-023, Baffle Former Bolts Alternate Aging Management Strategy2023-09-11011 September 2023 Baffle Former Bolts Alternate Aging Management Strategy IR 05000282/20230052023-08-30030 August 2023 Updated Inspected Plan for Prairie Island Nuclear Generating Plant Report 05000282/2023005 and 05000306/2023005 IR 05000282/20230102023-08-17017 August 2023 NRC Inspection Report 05000282/2023010 and 05000306/2023010 ML23222A0122023-08-10010 August 2023 Independent Spent Fuel Storage Installation and Monticello Nuclear Generating Plant - Changes in Foreign Ownership, Control or Influence IR 05000282/20230022023-08-0303 August 2023 Integrated Inspection Report 05000282/2023002 and 05000306/2023002 ML23214A2032023-08-0202 August 2023 Request for Information for an NRC Quadrennial Comprehensive Engineering Team Inspection: Inspection Report 05000282/2024010; 05000306/2024010 ML23206A2342023-07-25025 July 2023 Independent Spent Fuel Storage Installation, and Monticello Nuclear Generating Plant, Changes in Foreign Ownership, Control or Influence ML23202A0032023-07-21021 July 2023 Independent Spent Fuel and Independent Spent Fuel Storage Installation, Monticello Nuclear Generating Plant, Submittal of Quality Assurance Topical Report (NSPM-1) ML23199A0922023-07-18018 July 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000306/2023004 ML23195A1732023-07-14014 July 2023 Revision of Standard Practice Procedures Plan L-PI-23-018, License Amendment Request to Revise ISFSI Technical Specification 4.4 to Allow Use of a Code Alternative to ASME Code, NB-5130, Examination of Weld Edge Preparation Surfaces, for the TN-40HT2023-07-14014 July 2023 License Amendment Request to Revise ISFSI Technical Specification 4.4 to Allow Use of a Code Alternative to ASME Code, NB-5130, Examination of Weld Edge Preparation Surfaces, for the TN-40HT ML23181A0192023-06-30030 June 2023 Independent Spent Fuel Storage Installation, Revision to Correspondence Service List for Northern States Power - Minnesota ML23178A2422023-06-28028 June 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III L-PI-23-006, License Amendment Request to Revise Technical Specification 3.7.8 Required Actions2023-06-22022 June 2023 License Amendment Request to Revise Technical Specification 3.7.8 Required Actions L-PI-23-016, 2022 10 CFR 50.46 LOCA Annual Report2023-06-14014 June 2023 2022 10 CFR 50.46 LOCA Annual Report IR 05000282/20234202023-06-0101 June 2023 Security Baseline Inspection Report 05000282/2023420 and 05000306/2023420 ML23150A1722023-05-30030 May 2023 Preparation and Scheduling of Operator Licensing Examinations 2024-02-01
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 October 9, 2013 Mr. James E. Lynch Site Vice President Northern States Power Company - Minnesota Prairie Island Nuclear Generating Plant 1717 Wakonade Drive East Welch, MN 55089-9642
SUBJECT:
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)
Dear Mr. Lynch:
By letter dated September 28, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12278A405), Northern States Power Company, a Minnesota corporation (NSPM, the licensee), doing business as Xcel Energy, submitted a license amendment request (LAR) to transition its fire protection licensing basis at the Prairie Island Nuclear Generating Plant, Units 1 and 2, from paragraph 50.48(b) of Title 10 of the Code of Federal Regulations (10 CFR) to 10 CFR 50.48(c), National Fire Protection Association Standard NFPA 805 (NFPA 805).
By letters dated November 8, 2012, and December 18, 2012 (ADAMS Accession Nos*.
ML12314A144 and ML12354A464, respectively), NSPM provided supplemental information in support of its application. By letter dated January 2, 2013 (ADAMS Accession No. ML13002A209), the NRC informed NSPM that it had accepted the application for review.
Subsequent to the acceptance of the application, NSPM staff verbally informed the NRC staff that, in preparation for the NRC Audit of the PINGP NFPA 805 LAR, it had identified a number of issues associated with the Fire Probabilistic Risk Assessment (PRA) that NSPM had determined to affect the risk values identified in the September 28, 2012, application and the December 18, 2012, supplemental letter. Subsequently, by letter dated May 3, 2013 (ADAMS Accession No. ML13126A115), NSPM informed the NRC that a revision to the PRA was necessary and provided a commitment to provide a supplement to the NFPA 805 LAR with revised Fire PRA results by May 1, 2014.
On October 8, 2013, during a telephone call between the NSPM staff and the NRC staff, it was agreed that:
- 1. The NRC staff will not resume the review of the PINGP NFPA 805 application until the licensee provides the supplemental information as described in its May 3, 2013, letter.
- 2. The licensee will provide the NRC staff with a schedule and interim milestones for submitting the supplement to the NFPA 805 LAR within 14 days from the date of this letter.
J. E. Lynch 3. The NRC will conduct monthly conference calls with NSPM to discuss the progress of NSPM's supplement development with respect to the milestone schedules.
If you have any questions, please contact me at (301) 415-4037 or via e-mail at thomas. wengert@nrc.gov.
Sincerely, (f"~J thomas J. Wengert, Senior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-282 and 50-3.06 cc: Distribution via ListServ
J. E. Lynch 3. The NRC will conduct monthly conference calls with NSPM to discuss the progress of NSPM's supplement development with respect to the milestone schedules.
If you have any questions, please contact me at (301) 415-4037 or via e-mail at thomas.wengert@nrc.gov.
Sincerely,
/RAJ Scott P. Wall for Thomas J. Wengert, Senior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-282 and 50-306 cc: Distribution via ListServ DISTRIBUTION: ,
PUBLIC LPL3-1 RJF RidsNrrDorllpl3-1 Resource RidsNrrPMPrairielsland Resource RidsNrrLAMHenderson Resource
.RidsAcrsAcnw_MaiiCTR Resource RidsNrrDraAfpb Reource RidsRgn3MaiiCenter Resource RidsNrrDraApla Resource ADAMS Accession Number* ML13282A538 OFFICE LPL3-1/PM LPL3-1/BC NAME TWengert RCarlson (SWall for)
DATE 10/09/13 10/09/13 OFFICIAL RECORD COPY