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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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Text
rch 3, 2010
SUBJECT:
ANNUAL ASSESSMENT LETTER - PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 (05000282/2010001; 05000306/2010001)
Dear Mr. Schimmel:
On February 11, 2010, the NRC staff completed its performance review of Prairie Island Generating Plant, Units 1 and 2. Our technical staff reviewed performance indicators (PIs)
for the most recent quarter and inspection results for the period from January 1 through December 31, 2009. The purpose of this letter is to inform you of our assessment of your safety performance during this period and our plans for future inspections at your facility.
This performance review and enclosed inspection plan do not include security information. A separate letter designated and marked as "Official Use Only - Security Information" will include the Security Cornerstone review and resultant inspection plan.
Overall, Prairie Island Nuclear Generating Plant, Units 1 and 2, operated in a manner that preserved public health and safety and fully met all cornerstone objectives. Plant performance for the most recent quarter at Prairie Island, Unit 1, was within the Regulatory Response Column of the NRCs Action Matrix based on one inspection finding in the Public Radiation Safety Cornerstone, from the first quarter of 2009, which involved a radioactive material shipment from your facility that did not conform to the applicable Department of Transportation (DOT) regulatory requirements when it arrived at the shipping destination. The supplemental inspection (95001) was successfully completed on December 4, 2009. Also, during this assessment period, the White finding in the Mitigating Systems Cornerstone (from the fourth quarter of 2008) involving the failure of the turbine driven auxiliary feedwater (TDAFW) pump to operate following a valid start signal was closed after the successful completion of a supplemental inspection (95001) on September 4, 2009. Based on the results of the two supplemental inspections performed during this assessment period, Unit 1 will move to the Licensee Response Column starting the first quarter of 2010. Plant performance for Prairie Island Unit 2 for the most recent quarter was also within the Regulatory Response Column of the NRCs Action Matrix based on two inspection findings (one in the Mitigating Systems Cornerstone and one in the Public Radiation Safety Cornerstone)
being classified as having low to moderate safety significance (White). The White finding in the Mitigating Systems Cornerstone, from the third quarter of 2009, is related to inadequate design of the component cooling water system. The inspection finding in the Public Radiation Safety Cornerstone being classified as having low to moderate safety significance (White) is the same as discussed above.
We plan to conduct a supplemental inspection (95001) in response to the White finding in the Mitigating Systems Cornerstone. Please notify us of your readiness to conduct this supplemental inspection. This supplemental inspection is in addition to Reactor Oversight Process (ROP) baseline inspections at your facility.
In the 2009 mid-cycle assessment letter, dated September 1, 2009 (ADAMS Ref.
ML092440367), we advised you of a substantive cross-cutting issue (SCCI) in the area of human performance (HP) with cross-cutting themes in the aspects of systematic process (H.1(a)), conservative assumptions (H.1(b)), procedural adequacy (H.2(c)), and procedural compliance (H.4(b)). During this assessment period, there were 26 findings documented with cross-cutting aspects in the HP area. Of these 26 findings, four shared a common cross-cutting aspect of systematic process, four findings with conservative assumptions, six findings with procedural adequacy, and seven findings with procedural compliance. The number of findings in the SCCI themes increased during this assessment period in two out of the four themes. You discussed your actions to address the ongoing HP SCCI during a December 1, 2009, public meeting and some improvement has been observed. However, these actions have not yet proven effective in mitigating the cross-cutting themes. Therefore, the NRC has a concern with your progress in addressing this cross-cutting area and has concluded that the SCCI will remain open until all cross-cutting themes have been cleared in the area of HP. To clear each of the themes, we will assess whether your corrective actions have resulted in a positive sustainable improvement in the area and will consider the number of findings in the theme.
In addition, because you have a substantive cross-cutting issue in the area of HP for two consecutive assessment cycles, we are requesting you provide a written response to the issue to include discussion of your actions undertaken, those actions planned to address the concern, and a current assessment of performance. This response should be sent to the NRC within 30 days of receipt of this letter. Also, we will discuss the substantive cross-cutting issue during the upcoming end-of-cycle meeting.
Additionally, on September 3, 2009, the staff issued a Severity Level III Notice of Violation in accordance with the NRCs Enforcement Policy. The violation was associated with a failure to provide complete and accurate information (10 CFR 50.9) regarding the medical condition of a senior reactor operator. In a letter dated September 30, 2009, you provided your response to this violation, as well as your corrective actions. The NRC plans to perform a follow up inspection on the actions taken during the first quarter of 2010. The enclosed inspection plan details the inspections, less those related to physical protection, scheduled through June 30, 2011. We also plan on performing several special and infrequently performed inspections that include: Inspection Procedure (IP) 92709, Licensee Strike Contingency Plans, and IP 92702, Follow up on Traditional Enforcement Actions, Including Violations, Deviations, Confirmatory Orders, and Alternative Dispute Resolution Confirmatory Action Letters. The inspection plan is provided to allow for the resolution of any scheduling conflicts and personnel availability issues well in advance of inspector arrival onsite. Routine resident inspections are not listed due to their ongoing and continuous nature. The inspections in the last 9 months of the inspection plan are tentative and may be revised at the mid-cycle review.
In accordance with 10 CFR 2.390 of the NRC=s ARules of Practice,@ a copy of this letter and its enclosure will be made 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).
If circumstances arise which cause us to change the inspection plan, we will contact you to discuss the change as soon as possible. Please contact John (Jack) B. Giessner at 630-829-9619 with any questions you may have regarding this letter or the inspection plan.
Sincerely,
/lRA/
Steven West, Director Division of Reactor Projects Docket Nos. 50-282; 50-306;72-010 License Nos. DPR-42; DPR-60; SNM-2506 Enclosure: Prairie Island Inspection/Activity Plan cc w/encl: Distribution via ListServ
Prairie Island Inspection / Activity Plan 03/01/2010 - 06/30/2011 Planned Dates No. of Staff Start End Inspection Activity Title on Site BI ENG - TRIENNIAL HEAT SINK INSPECTION 3 02/01/2010 03/12/2010 IP 7111107T Heat Sink Performance OL EXAM - PR. ISLAND INIT EXAM - APRIL 2010 3 03/15/2010 03/26/2010 W90224 OL - INITIAL EXAM - APRIL 2010 - PRAI BI RP - RADIATION PROTECTION BASELINE INSPECTION 1 03/22/2010 03/26/2010 IP 71124.01 Radiological Hazard Assessment and Exposure Controls BI RP - RADIATION PROTECTION BASELINE INSPECTION 1 04/26/2010 04/30/2010 IP 71124.08 Radioactive Solid Waste Processing and Radioactive Material Handling, Storage, and Transportation BI ENG - ENGINEERING INSERVICE INSPECTION 1 04/26/2010 05/28/2010 IP 7111108P Inservice Inspection Activities - PWR BI ENG - COMPONENT DESIGN BASES INSPECTION 6 06/28/2010 07/30/2010 IP 7111121 Component Design Bases Inspection PI&R - BIENNIAL PI&R INSPECTION 4 09/20/2010 10/08/2010 IP 71152B Identification and Resolution of Problems BI RP - RADIATION PROTECTION BASELINE INSPECTION 1 07/12/2010 07/16/2010 IP 71124.02 Occupational ALARA Planning and Controls BI RP - RADIATION PROTECTION BASELINE INSPECTION 1 08/09/2010 08/13/2010 IP 2515/173 Review of the Implementation of the Industry Ground Water Protection Voluntary Initiative 08/09/2010 08/13/2010 IP 71151-BI01 Reactor Coolant System Activity 08/09/2010 08/13/2010 IP 71151-OR01 Occupational Exposure Control Effectiveness 08/09/2010 08/13/2010 IP 71151-PR01 RETS/ODCM Radiological Effluent STRIKE - STRIKE CONTINGENCY-OPS/MAINT/RP/ENGR/QC 2 08/02/2010 12/31/2010 IP 92709 Licensee Strike Contingency Plans BI EP - EP EXERCISE / PI VERIFICATION 3 08/23/2010 08/27/2010 IP 7111401 Exercise Evaluation 08/23/2010 08/27/2010 IP 71151-EP01 Drill/Exercise Performance 08/23/2010 08/27/2010 IP 71151-EP02 ERO Drill Participation 08/23/2010 08/27/2010 IP 71151-EP03 Alert & Notification System BI RP - RADIATION PROTECTION BASELINE INSPECTION 1 11/01/2010 11/05/2010 IP 71124.05 Radiation Monitoring Instrumentation BI RP - RADIATION PROTECTION BASELINE INSPECTION 1 02/21/2011 02/25/2011 IP 2515/179 Verification of Licensee Responses to NRC Requirement for Inventories of Materials Tracked in NSTS 02/21/2011 02/25/2011 IP 71124.01 Radiological Hazard Assessment and Exposure Controls BI ENG - ENGINEERING INSERVICE INSPECTION - U1 1 04/30/2011 06/04/2011 IP 7111108P Inservice Inspection Activities - PWR
Prairie Island Inspection / Activity Plan 03/01/2010 - 06/30/2011 Planned Dates No. of Staff Start End Inspection Activity Title on Site BI RP - RADIATION PROTECTION BASELINE INSPECTION 1 05/02/2011 05/06/2011 IP 71124.03 In-Plant Airborne Radioactivity Control and Mitigation 05/02/2011 05/06/2011 IP 71124.04 Occupational Dose Assessment BI EP - EP ROUTINE INSPECTION / PI VERIFICATION 2 06/13/2011 06/17/2011 IP 7111402 Radiological Environmental Monitoring Program 06/13/2011 06/17/2011 IP 7111403 Emergency Response Organization Augmentation Testing 06/13/2011 06/17/2011 IP 7111405 Correction of Emergency Preparedness Weaknesses and Deficiencies 06/13/2011 06/17/2011 IP 71151-EP01 Drill/Exercise Performance 06/13/2011 06/17/2011 IP 71151-EP02 ERO Drill Participation 06/13/2011 06/17/2011 IP 71151-IE03 Unplanned Power Changes per 7000 Critical Hrs