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| {{#Wiki_filter:==SUBJECT:== | | {{#Wiki_filter:UNITED STATES ber 1, 2011 |
| MID-CYCLE LETTER FOR PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 | | |
| ; 05000282/2011-006; 05000306/2011-006 | | ==SUBJECT:== |
| | MID-CYCLE LETTER FOR PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2; 05000282/2011-006; 05000306/2011-006 |
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| ==Dear Mr. Schimmel:== | | ==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, 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. | | 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. |
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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
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| =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
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| =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
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| =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
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| , from the second quarter of 2011
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| , 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 [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
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| ," 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
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| , 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-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. | | 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). |
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| We also plan on performing a special and infrequently performed inspection: Inspection Procedure (IP) 71003, "Post Approval License Renewal
| | 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). |
| - 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-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.
| | 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. |
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| Results of these inspections can be found here: http://www.nrc.gov/japan/japan-activities.html
| | The enclosed inspection plan lists the inspections scheduled through December 31, 2012. |
| . 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."
| | 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. |
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| The NRC is currently reviewing the Task Force's recommendations to determine what additional actions may be warranted. | | 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. |
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| In accordance with 10 CFR 2.390 of the NRC | | 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. |
| =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. | |
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| Sincerely, | | Sincerely, |
| /RA/ | | /RA/ |
| Steven West , Director Division of Reactor Projects | | 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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| Docket Nos. | |
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| 50-282; 50-306 License Nos. | |
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| DPR-42; DPR-60 Enclosure: | |
| Prairie Island Inspection/Activity Plan | |
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| cc w/encl: Distribution via ListServ | |
| }} | | }} |
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Category:Inspection Plan
MONTHYEARIR 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 IR 05000282/20070012007-03-0202 March 2007 (EOC) Power Plant Assessment Letter (Report 05000282/2007001; 05000306/2007001) ML0624303382006-08-31031 August 2006 8/31/06 Prairie Island Station-Mid-Cycle Performance Reveiw and Inspection Plan 2023-08-30
[Table view] 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
[Table view] |
Text
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