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{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION REGION III 2443 WARRENVILLE ROAD, SUITE 210 LISLE, IL 60532-4352 March 3, 2010 Mr. Mark Site Vice President Prairie Island Nuclear Generating Plant Northern States Power Company, Minnesota 1717 Wakonade Drive East Welch, MN 55089
{{#Wiki_filter:rch 3, 2010


SUBJECT: ANNUAL ASSESSMENT LETTER - PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 (05000282/2010001;  
==SUBJECT:==
 
ANNUAL ASSESSMENT LETTER - PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 (05000282/2010001; 05000306/2010001)
05000306/2010001)


==Dear Mr. Schimmel:==
==Dear Mr. Schimmel:==
Line 30: Line 29:
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.
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 NRC's 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 conf orm 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  
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.


Regulatory Response Column of the NRC's 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.


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.


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.
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  
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.


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 NRC's 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  
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.


review. 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 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).
=s A Rules 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.
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,
Sincerely,
/lRA/ Steven West, Director  
/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
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  
 
Inspection / Activity Plan Page 1 of 2 02/24/2010 Report 22 03/01/2010-06/30/2011 Unit Number Planned Dates Start End Inspection Activity Title No. of Staff on Site Prairie Island BI ENG-TRIENNIAL HEAT SINK INSPECTION 3 1 IP Heat Sink Performance 7111107T 02/01/2010 03/12/2010 OL EXAM-PR. ISLAND INIT EXAM - APRIL 2010 3 1 OL - INITIAL EXAM - APRIL 2010 - PRAI W90224 03/15/2010 03/26/2010 BI RP-RADIATION PROTECTION BASELINE INSPECTION 1 1 IP Radiological Hazard Assessment and Exposure Controls 71124.01 03/22/2010 03/26/2010 BI RP-RADIATION PROTECTION BASELINE INSPECTION 1 1 IP Radioactive Solid Waste Processing and Radioactive Material Handling, Storage, and Transportation 71124.08 04/26/2010 04/30/2010 BI ENG-ENGINEERING INSERVICE INSPECTION 1 2 IP Inservice Inspection Activities - PWR 7111108P 04/26/2010 05/28/2010 BI ENG-COMPONENT DESIGN BASES INSPECTION 6 1 IP Component Design Bases Inspection 7111121 06/28/2010 07/30/2010 PI&R-BIENNIAL PI&R INSPECTION 4 1, 2 IP Identification and Resolution of Problems 71152B 09/20/2010 10/08/2010 BI RP-RADIATION PROTECTION BASELINE INSPECTION 1 1 IP Occupational ALARA Planning and Controls 71124.02 07/12/2010 07/16/2010 BI RP-RADIATION PROTECTION BASELINE INSPECTION 1 1 IP Review of the Implementation of the Industry Ground Water Protection Voluntary Initiative 2515/173 08/09/2010 08/13/2010 1 IP Reactor Coolant System Activity 71151-BI01 08/09/2010 08/13/2010 1 IP Occupational Exposure Control Effectiveness 71151-OR01 08/09/2010 08/13/2010 1 IP RETS/ODCM Radiological Effluent 71151-PR01 08/09/2010 08/13/2010 STRIKE-STRIKE CONTINGENCY-OPS/MAINT/RP/ENGR/QC 2 1 IP Licensee Strike Contingency Plans 92709 08/02/2010 12/31/2010 BI EP-EP EXERCISE / PI VERIFICATION 3 1 IP Exercise Evaluation 7111401 08/23/2010 08/27/2010 1 IP Drill/Exercise Performance 71151-EP01 08/23/2010 08/27/2010 1 IP ERO Drill Participation 71151-EP02 08/23/2010 08/27/2010 1 IP A lert & Notification System 71151-EP03 08/23/2010 08/27/2010 BI RP-RADIATION PROTECTION BASELINE INSPECTION 1 1 IP Radiation Monitoring Instrumentation 71124.05 11/01/2010 11/05/2010 BI RP-RADIATION PROTECTION BASELINE INSPECTION 1 1 IP Verification of Licensee Responses to NRC Requirement for Inventories of Materials Tracked in NSTS 2515/179 02/21/2011 02/25/2011 1 IP Radiological Hazard Assessment and Exposure Controls 71124.01 02/21/2011 02/25/2011 BI ENG-ENGINEERING INSERVICE INSPECTION - U1 1 1 IP Inservice Inspection Activities - PWR 7111108P 04/30/2011 06/04/2011 This report does not include INPO and OUTAGE activities.
 
This report shows only on-site and announced inspection procedures.


Inspection / Activity Plan Page 2 of 2 02/24/2010 Report 22 03/01/2010-06/30/2011 Unit Number Planned Dates Start End Inspection Activity Title No. of Staff on Site Prairie Island BI RP-RADIATION PROTECTION BASELINE INSPECTION 1 1 IP In-Plant Airborne Radioactivity Control and Mitigation 71124.03 05/02/2011 05/06/2011 1 IP Occupational Dose Assessment 71124.04 05/02/2011 05/06/2011 BI EP-EP ROUTINE INSPECTION / PI VERIFICATION 2 1 IP Radiological Environmental Monitoring Program 7111402 06/13/2011 06/17/2011 1 IP Emergency Response Organization Augmentation Testing 7111403 06/13/2011 06/17/2011 1 IP Correction of Emergency Preparedness Weaknesses and Deficiencies 7111405 06/13/2011 06/17/2011 1 IP Drill/Exercise Performance 71151-EP01 06/13/2011 06/17/2011 1 IP ERO Drill Participation 71151-EP02 06/13/2011 06/17/2011 1 IP Unplanned Power Changes per 7000 Critical Hrs 71151-IE03 06/13/2011 06/17/2011 This report does not include INPO and OUTAGE activities.
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


This report shows only on-site and announced inspection procedures.
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
}}
}}

Revision as of 21:24, 13 November 2019

03/03/2010, Prairie Island Power Plant EOC Assessment Letter (05000282-10-001; 05000306-10-001)
ML100610286
Person / Time
Site: Prairie Island  Xcel Energy icon.png
Issue date: 03/03/2010
From: Stephanie West
Division Reactor Projects III
To: Schimmel M
Northern States Power Co
References
FOIA/PA-2010-0209, IR-10-001
Download: ML100610286 (7)
v • d • e


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

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