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| | issue date = 09/01/2011 | | | issue date = 09/01/2011 |
| | title = Mid-Cycle Letter for Prairie Island Nuclear Plant, Units 1 and 2, 05000282-11-006; 05000306-11-006 | | | title = Mid-Cycle Letter for Prairie Island Nuclear Plant, Units 1 and 2, 05000282-11-006; 05000306-11-006 |
| | author name = West S K | | | author name = West S |
| | author affiliation = NRC/RGN-III/DRP | | | author affiliation = NRC/RGN-III/DRP |
| | addressee name = Schimmel M A | | | addressee name = Schimmel M |
| | addressee affiliation = Northern States Power Co | | | addressee affiliation = Northern States Power Co |
| | docket = 05000282, 05000306 | | | docket = 05000282, 05000306 |
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| =Text= | | =Text= |
| {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION REGION III 2443 WARRENVILLE ROAD, SUITE 210 LISLE, IL 60532 | | {{#Wiki_filter:UNITED STATES ber 1, 2011 |
| -4352 September 1 , 2 011 Mr. Mark Site Vice President Prairie Island Nuclear Generating Plant Northern States Power Company, Minnesota 1717 Wakonade Drive East Welch, MN 55089
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| SUBJECT: MID-CYCLE LETTER FOR PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 | | ==SUBJECT:== |
| ; 05000282/2011 | | MID-CYCLE LETTER FOR PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2; 05000282/2011-006; 05000306/2011-006 |
| -006; 05000306/2011 | |
| -006 | |
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| ==Dear Mr. Schimmel:== | | ==Dear Mr. Schimmel:== |
| On August 10 , 2011, the NRC completed its mid | | On August 10, 2011, the NRC completed its mid-cycle performance review of Prairie Island Nuclear Generating Plant, Units 1 and 2. The NRC reviewed the most recent quarterly performance indicators (PIs) in addition to inspection results and enforcement actions from July 1, 2010 through June 30, 2011. This letter informs you of the NRCs assessment of your facility during this period and its plans for future inspections at your facility. This performance review and enclosed inspection plan do not include security information. A separate letter will include the NRCs assessment of your performance in the Security Cornerstone and its security-related inspection plan. |
| -cycle performance review of Prairie Island Nuclear Generating Plant, Units 1 and 2. The NRC reviewed the most recent quarterly performance indicators (PIs) in addition to inspection results and enforcement actions from July 1, 20 10 through June 30, 20 11. This letter informs you of the NRC's assessment of your facility during this period and its plans for future inspections at your facility. This performance review and enclosed inspection plan do not include security information. A separate letter will include the NRC's assessment of your performance in the Security Cornerstone and its security | |
| -related inspection plan. | |
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| The NRC determined the performance at Prairie Island Nuclear Generating Plant, Unit 2 , during the most recent quarter was within the Licensee Response Column of the NRC | | The NRC determined the performance at Prairie Island Nuclear Generating Plant, Unit 2, during the most recent quarter was within the Licensee Response Column of the NRC=s Reactor Oversight Process (ROP) Action Matrix because all inspection findings had very low (i.e., green) safety significance, and all PIs indicated that your performance was within the nominal, expected range (i.e., green). Therefore, the NRC plans to conduct ROP baseline inspections at your facility (for Unit 2). |
| =s Reactor Oversight Process (ROP) Action Matrix because all inspection findings had very low (i.e., green) safety significance, and all PIs indicated that your performance was within the nominal, expected range (i.e., green). Therefore, the NRC plans to conduct ROP baseline inspections at your facility (for Unit 2). | |
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| The NRC determined the performance at Prairie Island Nuclear Generating Plant, Unit 1, was within the Licensee Response Column of the NRC | | The NRC determined the performance at Prairie Island Nuclear Generating Plant, Unit 1, was within the Licensee Response Column of the NRC=s ROP Action Matrix the first three quarters of the assessment period because all inspection findings had very low (i.e., green) safety significance and all PIs indicated that your performance was within the nominal, expected range (i.e., green). The NRC determined the performance during the most recent quarter was within the Regulatory Response Column of the NRC=s Reactor Oversight Process (ROP) Action Matrix because of one inspection finding in the Mitigating Systems Cornerstone being classified as having low-to-moderate significance (i.e., white). This finding, from the second quarter of 2011, involved both trains of safety-related battery chargers being susceptible to locking up (i.e., stop providing an output, if the incoming alternating current voltage dropped below the nameplate minimum voltage at the battery charger motor control center during certain design basis events). |
| =s ROP Action Matrix the first three quarters of the assessment period because all inspection findings had very low (i.e., green) safety significance and all PIs indicated that your performance was within the nominal, expected range (i.e., green). The NRC determined the performance during the most recent quarter was within the Regulatory Response Column of the NRC | |
| =s Reactor Oversight Process (ROP) Action Matrix because of one inspection finding in the Mitigating Systems Cornerstone being classified as having low | |
| -to-moderate significance (i.e., white). This finding | |
| , from the second quarter of 2011 | |
| , involved both trains of safety | |
| -related battery chargers being susceptible to locking up (i.e., stop providing an output, if the incoming alternating current voltage dropped below the nameplate minimum voltage at the battery charger motor control center during certain design basis events). | |
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| Changes in your performance as reflected in the Action Matrix as a result of this finding are documented in the letter addressed to you dated, August 17, 2011 [ML 112290087]. Therefore, in addition to ROP baseline inspections, the NRC plans to conduct a supplemental inspection in accordance with Inspection Procedure 95001, "Supplemental Inspection for One or Two White Inputs in a Strategic Performance Area | | Changes in your performance as reflected in the Action Matrix as a result of this finding are documented in the letter addressed to you dated, August 17, 2011 [ML112290087]. Therefore, in addition to ROP baseline inspections, the NRC plans to conduct a supplemental inspection in accordance with Inspection Procedure 95001, Supplemental Inspection for One or Two White Inputs in a Strategic Performance Area, once your staff notifies the NRC of your readiness for it to conduct a supplemental inspection to review the actions taken to address the performance issues. The objectives of the Supplemental Inspection are to provide assurance that the root causes and contributing causes of the performance issue are understood, extent of condition and extent of cause are identified, and corrective actions implemented are sufficient to address the root and contributing causes to prevent recurrence. |
| ," once your staff notifies the NRC of your readiness for it to conduct a supplemental inspection to review the actions taken to address the performance iss ues. The objectives of the Supplemental Inspection are to provide assurance that the root causes and contributing causes of the performance issue are understood, extent of condition and extent of cause are identified | |
| , and corrective actions implemented are sufficient to address the root and contributing causes to prevent recurrence. | |
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| The enclosed inspection plan lists the inspections scheduled through December 31, 2012. Routine inspections performed by resident inspectors are not included in the inspection plan. The inspections listed during the last nine months of the inspection plan are tentative and may be revised at the end | | The enclosed inspection plan lists the inspections scheduled through December 31, 2012. |
| -of-cycle performance review. The NRC provides the inspection plan to allow for the resolution of any scheduling conflicts and personnel availability issues. The NRC will contact you as soon as possible to discuss changes to the inspection plan should circumstances warrant any changes.
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| We also plan on performing a special and infrequently performed inspection: Inspection Procedure (IP) 71003, "Post Approval License Renewal | | Routine inspections performed by resident inspectors are not included in the inspection plan. The inspections listed during the last nine months of the inspection plan are tentative and may be revised at the end-of-cycle performance review. The NRC provides the inspection plan to allow for the resolution of any scheduling conflicts and personnel availability issues. The NRC will contact you as soon as possible to discuss changes to the inspection plan should circumstances warrant any changes. We also plan on performing a special and infrequently performed inspection: Inspection Procedure (IP) 71003, Post Approval License Renewal - Outage. |
| - Outage." In the days following the Fukushima Daiichi nuclear accident in Japan, the Commission directed the staff to establish a senior | |
| -level agency task force to conduct a methodical and systematic review of the NRC's processes and regulations to determine whether the agency should make additional improvements to its regulatory system.
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| The NRC has since completed Temporary Instruction (TI) 183, "Follow | | In the days following the Fukushima Daiichi nuclear accident in Japan, the Commission directed the staff to establish a senior-level agency task force to conduct a methodical and systematic review of the NRCs processes and regulations to determine whether the agency should make additional improvements to its regulatory system. The NRC has since completed Temporary Instruction (TI) 183, Follow-up to Fukushima Daiichi Nuclear Station Fuel Damage Event, and TI-184, Availability and Readiness Inspection of Severe Accident Management Guidelines (SAMGs) at your facility. Results of these inspections can be found here: http://www.nrc.gov/japan/japan-activities.html. Additionally, on May 11, 2011, the agency issued NRC Bulletin 2011-01, Mitigating Strategies, to confirm compliance with Order EA-02-026, subsequently imposed license conditions, and 10 CFR 50.54(hh)(2), and to determine the status of licensee mitigating strategies programs. On July 12, 2011, the NRCs Task Force made its recommendations to the Commission in its report, Recommendations for Enhancing Reactor Safety in the 21st Century: The Near-Term Task Force Review of Insights from the Fukushima Daiichi Accident. The NRC is currently reviewing the Task Forces recommendations to determine what additional actions may be warranted. |
| -up to Fukushima Daiichi Nuclear Station Fuel Damage Event," and TI-184, "Availability and Readiness Inspection of Severe Accident Management Guidelines (SAMGs)" at your facility. | |
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| Results of these inspections can be found here: http://www.nrc.gov/japan/japan
| | In accordance with 10 CFR 2.390 of the NRC=s ARules of Practice,@ a copy of this letter will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). Please contact me or John Giessner, Chief, Branch 4, Division of Reactor Projects, at 630-829-9619 with any questions you have regarding this letter. |
| -activities.html
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| . Additionally, on May 11, 2011, the agency issued NRC Bulletin 2011 | |
| -01, "Mitigating Strategies," to confirm compliance with Order EA-02-026, subsequently imposed license conditions, and 10 CFR 50.54(hh)(2), and to determine the status of licensee mitigating strategies programs.
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| On July 12, 2011, the NRC's Task Force made its recommendations to the Commission in its report, "Recommendations for Enhancing Reactor Safety in the 21 st Century: The Near-Term Task Force Review of Insights from the Fukushima Daiichi Accident."
| | Sincerely, |
| | | /RA/ |
| The NRC is currently reviewing the Task Force's recommendations to determine what additional actions may be warranted.
| | Steven West, Director Division of Reactor Projects Docket Nos. 50-282; 50-306 License Nos. DPR-42; DPR-60 Enclosure: Prairie Island Inspection/Activity Plan cc w/encl: Distribution via ListServ |
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| In accordance with 10 CFR 2.390 of the NRC
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| =s ARules of Practice,@ a copy of this letter will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading
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| -rm/adams.html (the Public Electronic Reading Room). Please contact me or John Giessner, Chief, Branch 4
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| , Division of Reactor Projects
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| , at 630-829-9619 with any questions you have regarding this letter.
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| Sincerely,/RA/
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| Steven West , Director Division of Reactor Projects | |
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| Docket Nos. | |
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| 50-282; 50-306 License Nos. | |
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| DPR-42; DPR-60 | |
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| ===Enclosure:===
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| Prairie Island Inspection/Activity Plan | |
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| cc w/encl: Distribution via ListServ | |
| }} | | }} |
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Category:Inspection Plan
MONTHYEARIR 05000282/20240052024-08-28028 August 2024
Updated Inspection Plan and Assessment Follow-Up Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report 05000282/2024005 and 05000306/2024005)
IR 05000282/20230062024-02-28028 February 2024
Annual Assessment Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report 05000282/2023006 and 05000306/2023006)
IR 05000282/20230052023-08-30030 August 2023
Updated Inspected Plan for Prairie Island Nuclear Generating Plant Report 05000282/2023005 and 05000306/2023005
IR 05000282/20220062023-03-0101 March 2023
Annual Assessment Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report, Units 1 and 2 (Report 05000282/2022006 and 05000306/2022006)
ML23055B0562023-02-27027 February 2023
Request for Information for NRC Commercial Grade Dedication Inspection Inspection Report 05000282/2023010 and 05000306/2023010
IR 05000282/20220052022-08-29029 August 2022
Updated Inspection Plan for Prairie Island Nuclear Generating Plant (Report 05000282/2022005; 05000306/2022005)
ML22007A1542022-01-0707 January 2022
Notification of NRC Fire Protection Team Inspection Request for Information Inspection Report 05000282/2022010 and 05000306/2022010
ML21363A0542021-12-29029 December 2021
Prairie Nuclear Generating Plant - Request for Information for an NRC Triennial Heat Exchanger/Sink Performance Inspection and Request for Information; Inspection Report 05000282/2022002 05000306/2022002
IR 05000282/20210052021-09-0101 September 2021
Updated Inspection Plan for Prairie Island Nuclear Generating Plant Units 1 and 2 (Report 05000282/2021005 and 05000306/2021005)
IR 05000282/20200062021-03-0404 March 2021
Annual Assessment Letter for the Prairie Island Nuclear Generating Plant (Report 05000282/2020006 and 05000306/2020006)
ML21062A0532021-03-0202 March 2021
Information Request to Support Upcomng Problem Identification and Resolution (Pi&R) Inspection at the Prairie Island Nuclear Generating Plant
IR 05000282/20200052020-09-0101 September 2020
Updated Inspection Plan for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report 05000282/2020005 and 05000306/2020005)
ML20189A1782020-07-0606 July 2020
Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000282/2020004; 05000306/2020004
IR 05000282/20190062020-03-0303 March 2020
Annual Assessment Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report 05000282/2019006 and 05000306/2019006)
IR 05000282/20190052019-08-28028 August 2019
Updated Inspection Plan for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report 05000282/2019005; 05000306/2019005)
ML19136A1562019-05-15015 May 2019
Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection (Garza)
ML19071A3532019-03-12012 March 2019
Ltr. 03/12/19 Prairie Island Nuclear Generating Plant, Units 1 and 2 - Notification of NRC Triennial Fire Protection Baseline Inspection Request for Information; Inspection Report 05000282/2019012; 05000306/2019012 (DRS-A.Dahbur)
IR 05000282/20180062019-03-0404 March 2019
Annual Assessment Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report 05000282/2018006 and 05000306/2018006)
ML18324A6122018-11-20020 November 2018
Ltr. 11/20/18 Prairie Island Nuclear Generating Plant, Units 1 and 2 - Notification of an NRC Triennial Heat Sink Performance Inspection and Request for Information; Inspection Report 05000282/2019001 and 05000306/2019001 (DRS-N.Feliz-Adorn
IR 05000282/20180052018-08-28028 August 2018
Updated Inspection Plan for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report 05000282/2018005 and 05000286/2018005)
ML18156A5532018-06-0505 June 2018
Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000282/2018004; 05000306/2018004 (DRS-M.Holmberg)
IR 05000282/20170062018-03-0202 March 2018
Annual Assessment Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report 05000282/2017006; 05000306/2017006)
IR 05000282/20170052017-08-28028 August 2017
Updated Inspection Plan (Report 05000282/2017005 and 05000306/2017005)
IR 05000282/20160062017-03-0101 March 2017
Annual Assessment Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report 05000282/2016006)
ML16265A1652016-09-20020 September 2016
Notification of an NRC Triennial Heat Sink Performance Inspection and Request for Information; Inspection Report 05000282/2016004; 05000306/2016004 (Gfo)
IR 05000282/20160052016-08-31031 August 2016
Mid-Cycle Assessment Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report 05000282/2016005; 05000306/2016005)
ML16222A7022016-08-0909 August 2016
Notification of NRC Supplemental Inspection (95001) and Request for Information
IR 05000282/20150062016-03-0202 March 2016
Annual Assessment Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Inspection Report 05000282/2015006 and 05000306/2015006)
ML15261A7182015-09-15015 September 2015
Ltr. 09/15/2015 Prairie Island Nuclear Generating Plant, Units 1 and 2 - Notification of NRC Triennial Fire Protection Baseline Inspection Request for Information 05000282/2016008; 05000306/2016008. (Dxs)
IR 05000282/20150052015-09-0101 September 2015
Mid-Cycle Assessment Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report 05000282/2015005; 05000306/2015005)
IR 05000282/20140012015-03-0404 March 2015
Annual Assessment Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2, (Report 05000282/2014001 and 05000306/2014001)
ML14245A2012014-09-0202 September 2014
Mid-Cycle Assessment Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2
ML14209A9342014-07-28028 July 2014
Notification of NRC Inspection and Request for Information
IR 05000282/20130012014-03-0404 March 2014
Annual Assessment Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2(Report 05000282/2013001; 05000306/2013001)
ML13246A2392013-09-0303 September 2013
2013 Prairie Island MOC Letter Combined
ML13203A2862013-07-22022 July 2013
Notification of Baseline Inspection and Information Request
ML13077A4742013-03-18018 March 2013
Information Request for a Post-approval Site Inspection for License Renewal
IR 05000282/20120012013-03-0404 March 2013
Annual Assessment Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report 05000282/2012001 and 05000306/2012001)
ML12249A4252012-09-0404 September 2012
Mid-Cycle Assessment Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2
IR 05000282/20110072012-03-0505 March 2012
Annual Assessment Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report 05000282/2011007 and 05000306/2011007)
IR 05000282/20110062011-09-0101 September 2011
Mid-Cycle Letter for Prairie Island Nuclear Plant, Units 1 and 2, 05000282-11-006; 05000306-11-006
ML1106203132011-03-0404 March 2011
EOC Annual Assessment Letter and Inspection/Activity Plan
ML1024400922010-09-0101 September 2010
Mid-Cycle Performance Review and Inspection Plan - Prairie Island Nuclear Power Plant
IR 05000282/20100012010-03-0303 March 2010
Prairie Island Power Plant EOC Assessment Letter (05000282-10-001; 05000306-10-001)
ML0924403672009-09-0101 September 2009
Prairie Island - Mid-Cycle Performance Review and Inspection Plan
IR 05000282/20090012009-03-0404 March 2009
Annual Assessment Letter - Prairie Island Nuclear Generating Plant, Units 1 and 2 (05000282-09-001 and 050000306-09-001)
ML0824603142008-09-0202 September 2008
Prairie Island, Units 1 & 2 - Mid-Cycle Performance Review and Inspection Plan
IR 05000282/20080012008-03-0303 March 2008
Prairie Island, EOC Annual Assessment Letter (Inspection Report 05000282-08-001 and 05000306-08-001)
ML0735402802007-12-19019 December 2007
Change to the Inspection Plan 1/1/08 - 12/31/08
ML0724302372007-08-31031 August 2007
8/31/07 Prairie Island - Mid-Cycle Performance Review and Inspection Plan
2024-08-28
[Table view]
Category:Letter
MONTHYEARML24277A1012024-10-0303 October 2024
Closure of Interim Report of a Potential Deviation or Failure to Comply Associated with Bentley Systems Incorporated Autopipe Software
ML24241A1682024-09-23023 September 2024
Transmittal Letter Amendment No. 13 to Materials License No. Special Nuclear Material-2506 for the Prairie Island Independent Spent Fuel Storage Installation
05000282/LER-2024-001, Auxiliary Building Special Ventilation System Inoperable During Movement of Irradiated Fuel Assemblies2024-09-16016 September 2024
Auxiliary Building Special Ventilation System Inoperable During Movement of Irradiated Fuel Assemblies
IR 05000282/20243012024-09-13013 September 2024
NRC Initial License Examination Report 05000282/2024301 and 05000306/2024301
IR 05000282/20240052024-08-28028 August 2024
Updated Inspection Plan and Assessment Follow-Up Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report 05000282/2024005 and 05000306/2024005)
L-PI-24-040, Post-Submittal Package Letter2024-08-23023 August 2024
Post-Submittal Package Letter
IR 05000282/20245012024-08-0505 August 2024
Emergency Preparedness Inspection Report 05000282/2024501 and 05000306/2024501
ML24213A1592024-07-31031 July 2024
Operator Licensing Examination Approval - Prairie Island Nuclear Generating Plant
IR 05000282/20240022024-07-30030 July 2024
Integrated Inspection Report 05000282/2024002 and 05000306/2024002
ML24208A1502024-07-26026 July 2024
Independent Spent Fuel Storage Installation - Submittal of Quality Assurance Topical Report (NSPM-1)
ML24197A2012024-07-15015 July 2024
Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000282/2024004
L-PI-24-036, – Preparation and Scheduling of Operator Licensing Examinations2024-06-28028 June 2024
– Preparation and Scheduling of Operator Licensing Examinations
IR 05000282/20240102024-06-28028 June 2024
Comprehensive Engineering Team Inspection Report 05000282/2024010 and 05000306/2024010
ML24158A5912024-06-0606 June 2024
CFR 50.46 LOCA Annual Report
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
ML24155A1952024-05-31031 May 2024
Reactor Trip and Auto-Start Actuation of Auxiliary Feedwater Due to Loss of Suction to the 22 Main Feedwater Pump
ML24155A1922024-05-31031 May 2024
Refueling Outage Unit 2 R33 Owners Activity Report for Class 1, 2, 3 and Mc Inservice Inspections
ML24149A3712024-05-29029 May 2024
(Ping) - Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection
ML24262A1992024-05-29029 May 2024
L-PI-24-018 PINGP 75 Day Letter
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
ML24141A1292024-05-22022 May 2024
Northern States Power Company - Use of Encryption Software for Electronic Transmission of Safeguards Information
ML24141A0452024-05-20020 May 2024
Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection
ML24128A2572024-05-16016 May 2024
ISFSI A13 Acceptance Letter
IR 05000282/20240012024-05-15015 May 2024
Integrated Inspection Report 05000282/2024001 and 05000306/2024001
ML24130A2392024-05-0909 May 2024
2023 Annual Radioactive Effluent Report
ML24130A2362024-05-0909 May 2024
Independent Spent Fuel Storage Installation - 2023 Annual Radiological Environmental Monitoring Program Report
ML24071A1162024-05-0101 May 2024
Issuance of Amendment Nos. 244 and 232 Revise TS 3.7.8, Cooling Water (Cl) System
ML24128A0882024-04-30030 April 2024
Submittal of Updated Safety Analysis Report (Usar), Revision 38
ML24089A2382024-04-29029 April 2024
Summary of Nuclear Property Insurance
ML24121A0432024-04-29029 April 2024
Reactor Trip and Auto-Start Actuation of Auxiliary Feedwater Due to Loss of Suction to the 22 Main Feedwater Pump
IR 05000282/20244012024-04-25025 April 2024
– Security Baseline Inspection Report 05000282/2024401 and 05000306/2024401
ML24100A8042024-04-24024 April 2024
– Alternative Request RR-09 for Safety Injection and Volume Control System Category C Check Valve Inservice Testing
ML24114A0882024-04-23023 April 2024
Annual Report of Individual Monitoring for the Prairie Island Nuclear Generating Plant (PINGP)
ML24113A1182024-04-12012 April 2024
NRC Letter Re NRC Office of Investigations Report No. 3-2023-004
ML24100A1212024-04-0909 April 2024
Submittal of Revised Pressure and Temperature Limits Report
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)
ML24093A2832024-04-0202 April 2024
Nuclear Material Transaction Report
ML24089A2402024-03-29029 March 2024
Guarantee of Payment of Deferred Premiums
ML24060A1232024-03-27027 March 2024
to Request 1-RR-5-10 and 2-RR-5-10 Regarding Reactor Pressure Vessel Welds and Nozzle Welds
ML24081A1532024-03-21021 March 2024
Reactor Trip, Auxiliary Feedwater and Emergency Service Water System Actuation Due to Electrical Transient in DC Control Power Cables
ML24262A1512024-03-15015 March 2024
L-PI-24-011 150 Day Letter 2024 PINGP ILT NRC Exam
ML24010A0582024-03-0505 March 2024
Amendment No. 12 to Materials License No. Special Nuclear Material-2506 for the Prairie Island Independent Spent Fuel Storage Installation
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
IR 05000282/20230062024-02-28028 February 2024
Annual Assessment Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report 05000282/2023006 and 05000306/2023006)
ML24088A1102024-02-25025 February 2024
Fairbanks Morse (Fm) Part 21 Notification Report Number 23-01 Re Asco Stainless Steel Solenoid Valves
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
ML24040A1712024-02-0909 February 2024
Interim Report of a Potential Deviation or Failure to Comply Associated with Bentley Systems Incorporated Autopipe Software
IR 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)
2024-09-23
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UNITED STATES ber 1, 2011
SUBJECT:
MID-CYCLE LETTER FOR PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2; 05000282/2011-006; 05000306/2011-006
Dear Mr. Schimmel:
On August 10, 2011, the NRC completed its mid-cycle performance review of Prairie Island Nuclear Generating Plant, Units 1 and 2. The NRC reviewed the most recent quarterly performance indicators (PIs) in addition to inspection results and enforcement actions from July 1, 2010 through June 30, 2011. This letter informs you of the NRCs assessment of your facility during this period and its plans for future inspections at your facility. This performance review and enclosed inspection plan do not include security information. A separate letter will include the NRCs assessment of your performance in the Security Cornerstone and its security-related inspection plan.
The NRC determined the performance at Prairie Island Nuclear Generating Plant, Unit 2, during the most recent quarter was within the Licensee Response Column of the NRC=s Reactor Oversight Process (ROP) Action Matrix because all inspection findings had very low (i.e., green) safety significance, and all PIs indicated that your performance was within the nominal, expected range (i.e., green). Therefore, the NRC plans to conduct ROP baseline inspections at your facility (for Unit 2).
The NRC determined the performance at Prairie Island Nuclear Generating Plant, Unit 1, was within the Licensee Response Column of the NRC=s ROP Action Matrix the first three quarters of the assessment period because all inspection findings had very low (i.e., green) safety significance and all PIs indicated that your performance was within the nominal, expected range (i.e., green). The NRC determined the performance during the most recent quarter was within the Regulatory Response Column of the NRC=s Reactor Oversight Process (ROP) Action Matrix because of one inspection finding in the Mitigating Systems Cornerstone being classified as having low-to-moderate significance (i.e., white). This finding, from the second quarter of 2011, involved both trains of safety-related battery chargers being susceptible to locking up (i.e., stop providing an output, if the incoming alternating current voltage dropped below the nameplate minimum voltage at the battery charger motor control center during certain design basis events).
Changes in your performance as reflected in the Action Matrix as a result of this finding are documented in the letter addressed to you dated, August 17, 2011 [ML112290087]. Therefore, in addition to ROP baseline inspections, the NRC plans to conduct a supplemental inspection in accordance with Inspection Procedure 95001, Supplemental Inspection for One or Two White Inputs in a Strategic Performance Area, once your staff notifies the NRC of your readiness for it to conduct a supplemental inspection to review the actions taken to address the performance issues. The objectives of the Supplemental Inspection are to provide assurance that the root causes and contributing causes of the performance issue are understood, extent of condition and extent of cause are identified, and corrective actions implemented are sufficient to address the root and contributing causes to prevent recurrence.
The enclosed inspection plan lists the inspections scheduled through December 31, 2012.
Routine inspections performed by resident inspectors are not included in the inspection plan. The inspections listed during the last nine months of the inspection plan are tentative and may be revised at the end-of-cycle performance review. The NRC provides the inspection plan to allow for the resolution of any scheduling conflicts and personnel availability issues. The NRC will contact you as soon as possible to discuss changes to the inspection plan should circumstances warrant any changes. We also plan on performing a special and infrequently performed inspection: Inspection Procedure (IP) 71003, Post Approval License Renewal - Outage.
In the days following the Fukushima Daiichi nuclear accident in Japan, the Commission directed the staff to establish a senior-level agency task force to conduct a methodical and systematic review of the NRCs processes and regulations to determine whether the agency should make additional improvements to its regulatory system. The NRC has since completed Temporary Instruction (TI) 183, Follow-up to Fukushima Daiichi Nuclear Station Fuel Damage Event, and TI-184, Availability and Readiness Inspection of Severe Accident Management Guidelines (SAMGs) at your facility. Results of these inspections can be found here: http://www.nrc.gov/japan/japan-activities.html. Additionally, on May 11, 2011, the agency issued NRC Bulletin 2011-01, Mitigating Strategies, to confirm compliance with Order EA-02-026, subsequently imposed license conditions, and 10 CFR 50.54(hh)(2), and to determine the status of licensee mitigating strategies programs. On July 12, 2011, the NRCs Task Force made its recommendations to the Commission in its report, Recommendations for Enhancing Reactor Safety in the 21st Century: The Near-Term Task Force Review of Insights from the Fukushima Daiichi Accident. The NRC is currently reviewing the Task Forces recommendations to determine what additional actions may be warranted.
In accordance with 10 CFR 2.390 of the NRC=s ARules of Practice,@ a copy of this letter will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). Please contact me or John Giessner, Chief, Branch 4, Division of Reactor Projects, at 630-829-9619 with any questions you have regarding this letter.
Sincerely,
/RA/
Steven West, Director Division of Reactor Projects Docket Nos. 50-282; 50-306 License Nos. DPR-42; DPR-60 Enclosure: Prairie Island Inspection/Activity Plan cc w/encl: Distribution via ListServ
