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EPID:L-2022-LLA-0184, Application to Revise Technical Specification Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) (Approved, Closed) |
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MONTHYEARML22067A1482022-03-0707 March 2022 Reactor Vessel Material Surveillance Program Report Project stage: Request ML22153A1392022-05-31031 May 2022 WCAP-18124-NP-A, Revision 0, Supplement 1-NP-A, Revision 0, Fluence Determination with RAPTOR-M3G and Ferret - Supplement for Extended Beltline Materials Project stage: Request 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) Project stage: Request L-PI-23-002, WCAP-18795-NP, Revision 0, Analysis of Capsule N from the Xcel Energy Prairie Island Unit 2 Reactor Vessel Radiation Surveillance Program, (Part 7 of 7)2022-12-31031 December 2022 WCAP-18795-NP, Revision 0, Analysis of Capsule N from the Xcel Energy Prairie Island Unit 2 Reactor Vessel Radiation Surveillance Program, (Part 7 of 7) Project stage: Request ML23018A2952023-01-18018 January 2023 Acceptance of Requested Licensing Action to Revise Technical Specification 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) (EPID L-2022-LLA-0184) (Email) Project stage: Acceptance Review ML23020A9172023-01-26026 January 2023 Request for Withholding Information from Public Disclosure License Amendment Request to Revise Technical Specification Section 5.6.6, RCS PTLR Project stage: Withholding Request Acceptance 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) Project stage: Supplement ML23348A3472023-12-12012 December 2023 NRR E-mail Capture - (External_Sender) NRC Notification to the State of Minnesota Regarding a Prairie Island Nuclear Generating Plant, Units 1 & 2, Amendment Project stage: Other 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 Project stage: Response to RAI ML23356A0032024-01-17017 January 2024 Issuance of Amendments Revise Technical Specification 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) Project stage: Approval ML24271A2922024-11-20020 November 2024 – Correction of License Amendment Nos. 243 and 231 Revise Technical Specification 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) (EPID-L-2022-LLA-0184) Project stage: Other 2023-01-26
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1717 Wakonade Drive Welch, MN 55089 March 7, 2022 L-PI-22-005 10 CFR Part 50 Appendix H ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Prairie Island Nuclear Generating Plant, Unit 1 Docket No. 50-282 Renewed Facility Operating License No. DPR-42 Prairie Island Unit 1 Reactor Vessel Material Surveillance Program Report In accordance with 10 CFR 50 Appendix H, Northern States Power Company, a Minnesota corporation, doing business as Xcel Energy (hereafter NSPM), hereby submits the enclosed non-proprietary report WCAP-18660-NP, Analysis of Capsule N from the Xcel Energy Prairie Island Unit 1 Reactor Vessel Radiation Surveillance Program.
The enclosed report will result in changes to the Prairie Island Nuclear Generating Plant Pressure and Temperature Limits Report. Therefore, NSPM will submit a license amendment request (LAR) to TS 5.6.6, Reactor Coolant System (RCS) PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR), to incorporate use of newer approved analytical methods to determine the RCS pressure and temperature limits and Cold Overpressure Mitigation System setpoints. In accordance with 10 CFR 50, Appendix H, NSPM expects this LAR will be submitted by August 31, 2022.
Summary of Commitments This letter makes no new commitments and no revisions to existing commitments.
fl Xcel Energy
Document Control Desk Page 2 Please contact Mr. Jeff Kivi at (612) 330-5788 or Jeffrey.Kivi@xenuclear.com if there are any questions o i iti al information is needed.
Christopher. Domingos Site Vice President, Monticello and Prairie Island Nuclear Generating Plants Northern States Power Company - Minnesota Enclosure cc:
Administrator, Region Ill, USNRC Project Manager, Prairie Island, USNRC Resident Inspector, Prairie Island, USNRC
ENCLOSURE PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNIT 1 Prairie Island Unit 1 Reactor Vessel Material Surveillance Program Report (345 Pages Follow)