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Results
Other: ML20071C899, ML21049A307, ML21165A344, ML21201A105, ML21242A330, ML21253A113, ML21272A183, ML21279A167, ML21293A026, ML21295A412, ML21323A074, ML22040A158, ML22108A286, ML22145A020, ML22186A150, ML22187A277, ML22188A089, ML22189A177, ML23025A353
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MONTHYEARML20071C8992020-03-24024 March 2020 Closeout of Bulletin 2012-01, Design Vulnerability in Electric Power System Project stage: Other ML20365A0702020-12-30030 December 2020 Schedule Change to Open Phase Condition Detection Implementation Project stage: Request ML21049A3072021-03-0505 March 2021 Status of Closeout of Bulletin 2012-01, Design Vulnerability in Electric Power System Project stage: Other ML21165A3442021-06-29029 June 2021 Closeout of Bulletin 2012-01, Design Vulnerability in Electric Power System Project stage: Other ML21201A1052021-07-27027 July 2021 Closeout of Bulletin 2012-01, Design Vulnerability in Electric Power System Project stage: Other ML21242A3302021-09-14014 September 2021 Closeout of Bulletin 2012-01, Design Vulnerability in Electric Power System Project stage: Other ML21253A1132021-09-20020 September 2021 Closeout of Bulletin 2012-01, Design Vulnerability in Electric Power System Project stage: Other ML21272A1832021-10-19019 October 2021 Closeout of Bulletin 2012-01, Design Vulnerability in Electric Power System Project stage: Other ML21279A1672021-10-22022 October 2021 Closeout of Bulletin 2012-01, Design Vulnerability in Electric Power System Project stage: Other ML21293A0262021-10-27027 October 2021 Closeout of Bulletin 2012 01, Design Vulnerability in Electric Power System Project stage: Other ML21295A4122021-11-15015 November 2021 Closeout of Bulletin 2012-01, Design Vulnerability in Electric Power System Project stage: Other ML21323A0742021-11-22022 November 2021 Closeout of Bulletin 2012-01, Design Vulnerability in Electric Power System Project stage: Other ML22040A1582022-02-10010 February 2022 Closeout of Bulletin 2012 01, Design Vulnerability in Electric Power System Project stage: Other ML22108A2862022-04-29029 April 2022 Closeout of Bulletin 2012 01, Design Vulnerability in Electric Power System Project stage: Other ML22145A0202022-05-26026 May 2022 Closeout of Bulletin 2012-01, Design Vulnerability in Electric Power System Project stage: Other ML22186A1502022-07-0808 July 2022 Closeout of Bulletin 2012-01, Design Vulnerability in Electric Power System Project stage: Other ML22189A1772022-07-13013 July 2022 Closeout of Bulletin 2012 01, Design Vulnerability in Electric Power System Project stage: Other ML22187A2772022-07-19019 July 2022 Closeout of Bulletin 2012-01, Design Vulnerability in Electric Power System Project stage: Other ML22188A0892022-07-21021 July 2022 Closeout of Bulletin 2012 01, Design Vulnerability in Electric Power System Project stage: Other ML23025A3532023-01-26026 January 2023 Closeout of Bulletin 2012 01, Design Vulnerability in Electric Power System Project stage: Other 2021-07-27
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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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May 26, 2022 Mr. Christopher P. Domingos Site Vice President Northern States Power Company - Minnesota Prairie Island Nuclear Generating Plant 1717 Wakonade Drive East Welch, MN 55089
SUBJECT:
PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 -
CLOSEOUT OF BULLETIN 2012-01, DESIGN VULNERABILITY IN ELECTRIC POWER SYSTEM (EPID L-2017-CRS-0063)
Dear Mr. Domingos:
The purpose of this letter is to inform you that the U.S. Nuclear Regulatory Commission (NRC) staff has verified that Northern States Power Company (the licensee) has provided the necessary information requested in NRCs Bulletin (BL) 2012-01, Design Vulnerability in Electric Power System, dated July 27, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12074A115), for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Prairie Island). The NRC staff has completed its review of this information and this letter closes out BL 2012-01 for Prairie Island.
The NRC issued BL 2012-01 to all holders of operating licenses and combined licenses for nuclear power reactors, except those who have permanently ceased operation and have certified that fuel has been removed from the reactor vessel. The BL requested information about each facilitys electric power system designs that would allow the NRC staff to verify the systems capability to address open phase conditions. Specifically, the NRC requested licensees provide the following information:
A description of how the protection scheme for engineered safety features buses (Class 1E for currently operating plants) is designed to detect and automatically respond to a single-phase open circuit condition or high impedance ground fault condition on offsite power circuits or another power source; and A description of the operating configuration of engineered safety features buses (Class 1E for currently operating plants) at power (i.e., normal operating condition).
By letter dated October 18, 2012 (ML12318A285), the licensee provided its response to BL 2012-01 for Prairie Island. By letter dated February 3, 2014 (ML14034A066), the licensee provided supplemental information for Prairie Island in response to an NRC staff request for additional information issued on December 20, 2013 (ML13351A314).
By letters dated October 9, 2013, and March 16, 2015 (ML13333A147 and ML15075A454, respectively), the Nuclear Energy Institute (NEI) submitted a voluntary industry initiative to address open phase conditions at nuclear power plants. The NEI letter dated March 16, 2015,
C. Domingos stated, in part: The initiative is a formal commitment by the companies that operate nuclear power plants to follow a specific policy or plan of action. The initiative calls for a proactive plan and schedule for addressing potential design vulnerabilities to the open phase condition.
To evaluate the adequacy of the open phase isolation systems designs, the NRC staff issued Temporary Instruction (TI) 2515/194, Inspection of the Licensees Implementation of Industry Initiative Associated with the Open Phase Condition Design Vulnerabilities in Electric Power Systems (NRC Bulletin 2012-01), dated October 31, 2017 (ML17137A416), which provided temporary inspection instructions for the purpose of verifying that licensees appropriately implemented the NEI voluntary industry initiative dated March 16, 2015. The NRC staff piloted the use of TI 2515/194 by inspecting four nuclear power plants with four distinct open phase isolation system designs. A summary of the NRC staffs preliminary observations and issues needing additional clarity were discussed with industry representatives in two public meetings conducted on September 19, 2018, and October 17, 2018. The meeting summaries can be found in ADAMS under Package Accession Nos. ML18268A342 and ML18309A226, respectively.
By letter dated June 6, 2019 (ML19163A176), NEI submitted Revision 3 of the voluntary industry initiative to include an option for plants to perform a risk evaluation under certain boundary conditions to support manual response to an open phase condition. NEI also submitted NEI 19-02, Guidance for Assessing Open Phase Condition Implementation Using Risk Insights on June 20, 2019 (ML19172A086). On August 18, 2020, the NRC staff issued Revision 2 of TI 2515/194 (ML20230A328), which provided temporary inspection instructions for the purpose of verifying that licensees appropriately implemented Revision 3 of the NEI voluntary industry initiative. The revision accounted for changes reflected in Revision 3 of the NEI voluntary initiative.
In September 2021, the NRC staff performed an inspection at Prairie Island using TI 2515/194 Revision 2. The inspection was performed to verify the licensees implementation of the voluntary industry initiative at Prairie Island. To address the potential open phase condition design vulnerability issue at Prairie Island, the licensee implemented open phase isolation system plant modifications, which provide detection and alarm in the control room, and necessary plant procedures that allow operators to diagnose and take manual action to mitigate an open phase condition. The NRC staff documented the results of the TI 2515/194 inspection in a report dated October 27, 2021 (ML21299A295).
The NRC staff reviewed the information submitted by the licensee and the results of the TI 2515/194 inspection for Prairie Island. Two exceptions were identified in the inspection report: (1) the Updated Safety Analysis Report was not updated with complete description of the as-built configuration of the open phase detection system; and (2) maintenance for the open phase detection system has not been developed. The licensee captured these exceptions in their corrective action program. Based on this review, the NRC staff concludes that the licensee provided the necessary information requested in BL 2012-01 and has completed the implementation of its open phase isolation system. Therefore, the NRC staff closes BL 2012-01 for Prairie Island.
C. Domingos If you have any questions, please contact me at 301-415-3733 or Robert.Kuntz@nrc.gov.
Sincerely,
/RA/
Robert Kuntz, Senior Project Manager Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-282 and 50-306 cc: Listserv
ML22145A020 OFFICE NRR/DORL/LPL3/PM NRR/DORL/LPL3/LA NRR/DRO/IOEB/BC NAME RKuntz SRohrer LRegner DATE 5/25/2022 5/25/2022 5/25/2022 OFFICE NRR/DEX/EEEB/BC NRR/DRA/APOB/BC NRR/DORL/LPL3/BC NAME WMorton AZoulis NSalgado DATE 05/23/2022 5/25/2022 5/26/2022 OFFICE NRR/DORL/LPL3/PM NAME RKuntz DATE 5/26/2022