ML102440092
| ML102440092 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 09/01/2010 |
| From: | Stephanie West Division Reactor Projects III |
| To: | Schimmel M Northern States Power Co |
| References | |
| Download: ML102440092 (6) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION REGION III 2443 WARRENVILLE ROAD, SUITE 210 LISLE, IL 60532-4352 September 1, 2010 Mr. Mark A. Schimmel Site Vice President Prairie Island Nuclear Generating Plant Northern States Power Company, Minnesota 1717 Wakonade Drive East Welch, MN 55089
SUBJECT:
MID-CYCLE PERFORMANCE REVIEW AND INSPECTION PLAN -
PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2
Dear Mr. Schimmel:
On August 5, 2010, the NRC staff completed its performance review of Prairie Island Nuclear 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 July 1, 2009, through June 30, 2010. 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 for Prairie Island Unit 1 was within the Licensee Response column of the NRCs Action Matrix, based on all inspection findings being classified as having very low safety significance (Green) and all PIs indicating performance at a level requiring no additional NRC oversight (Green). Therefore, we plan to conduct reactor oversight process (ROP) baseline inspections at your facility.
Plant performance for Prairie Island Unit 2 for the most recent quarter was within the Regulatory Response Column of the NRCs Action Matrix based on one inspection finding in the Mitigating Systems Cornerstone being classified as having low-to-moderate safety significance (White).
This finding from the third quarter of 2009 was related to inadequate design of the component cooling water system. A supplemental inspection (95001) was performed the week of June 14-18, 2010. The results of this inspection will be documented in a future inspection report.
M. Schimmel Since the 2009 mid-cycle assessment letter, dated September 1, 2009 (ADAMS Ref. ML092440367), we have 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 16 findings documented with cross-cutting aspects in the HP area. Of these 16 findings, three shared a common cross-cutting aspect of systematic process, two findings with conservative assumptions, three findings with procedural adequacy, and three findings with procedural compliance.
With respect to the SCCI in conservative assumptions, H.1(b), both the NRC and your organization have noted an improvement in this area. Your staff has identified corrective actions that should reasonably address the SCCI. Additionally, the number of findings with a cross-cutting aspect in conservative assumptions has been reduced. For these reasons, the NRC has gained confidence in your ability to correct the concerns identified and sustained improvement has been observed in this aspect. Therefore, the SCCI aspect in conservative assumption (H.1(b)) is closed.
For the SCCI in the HP area related to the aspects of systematic process (H.1(a)), procedural adequacy (H.2(c)), and procedural compliance (H.4(b)), although the number of findings in all these SCCI themes decreased during this assessment, the overall number of findings related to HP has remained high. We recognize that you have initiated comprehensive measures to address this issue and improvement has been observed, but the high number of HP related findings indicates that these actions have not yet resulted in positive sustainable improvement in mitigating the cross-cutting themes. As a result, the SCCI will remain open. 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 had a substantive cross-cutting issue in the area of HP for three consecutive assessment cycles, we will be reviewing your recently completed independent safety culture assessment during the upcoming Problem Identification & Resolution inspection, which is scheduled for September 20 through October 8, 2010. Please notify us of your readiness to conduct the review of the safety culture assessment during this inspection.
Additionally, we are requesting to meet with you to discuss your progress in addressing the SCCI. A public meeting will accommodate this discussion at an agreed upon time and location.
Please contact us within 30 days of receipt of this letter to discuss arrangements for this meeting.
The enclosed inspection plan details the inspections, less those related to physical protection, scheduled through December 31, 2011. We also plan on performing several special and infrequently performed inspections that include: Inspection Procedure (IP) 92709, Licensee Strike Contingency Plans, and IP 60855.1, Operation of an Independent Spent Fuel Storage Installation at Operating Plants. 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 end-of-cycle review.
M. Schimmel 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 Robert Orlikowski at 630-829-9753 with any questions you may have regarding this letter or the inspection plan.
Sincerely,
/RA/
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
Inspection / Activity Plan 09/01/2010 - 12/31/2011 Planned Dates Start End Inspection Activity Title No. of Staff on Site Prairie Island PI&R
- BIENNIAL PI&R INSPECTION 6
IP Identification and Resolution of Problems 71152B 09/20/2010 10/08/2010 STRIKE
- STRIKE CONTINGENCY-OPS/MAINT/I&C/ENGR/QC 2
IP Licensee Strike Contingency Plans 92709 08/02/2010 12/31/2010 BI RP
- RADIATION PROTECTION BASELINE INSPECTION 1
IP Radiation Monitoring Instrumentation 71124.05 02/21/2011 02/25/2011 IP Reactor Coolant System Activity 71151-BI01 02/21/2011 02/25/2011 IP Occupational Exposure Control Effectiveness 71151-OR01 02/21/2011 02/25/2011 IP RETS/ODCM Radiological Effluent 71151-PR01 02/21/2011 02/25/2011 BI ENG
- INSERVICE INSPECTION - U1 1
IP Inservice Inspection Activities - PWR 7111108P 04/30/2011 06/04/2011 BI RP
- RADIATION PROTECTION BASELINE INSPECTION 1
IP Occupational ALARA Planning and Controls 71124.02 05/09/2011 05/13/2011 IP In-Plant Airborne Radioactivity Control and Mitigation 71124.03 05/09/2011 05/13/2011 BI EP
- EP ROUTINE INSPECTION / PI VERIFICATION 2
IP Alert and Notification System Testing 7111402 06/13/2011 06/17/2011 IP Emergency Preparedness Organization Staffing and Augmentation System 7111403 06/13/2011 06/17/2011 IP Correction of Emergency Preparedness Weaknesses and Deficiencies 7111405 06/13/2011 06/17/2011 IP Drill/Exercise Performance 71151-EP01 06/13/2011 06/17/2011 IP ERO Drill Participation 71151-EP02 06/13/2011 06/17/2011 IP Unplanned Power Changes per 7000 Critical Hrs 71151-IE03 06/13/2011 06/17/2011 BI RP
- RADIATION PROTECTION BASELINE INSPECTION 1
IP Radioactive Gaseous and Liquid Effluent Treatment 71124.06 06/20/2011 06/24/2011 IP Radiological Environmental Monitoring Program 71124.07 06/20/2011 06/24/2011 BI ENG
- MODIFICATIONS / 50.59 INSPECTION 3
IP Evaluations of Changes, Tests, or Experiments and Permanent Plant Modifications 7111117T 09/12/2011 09/30/2011 BI RP
- RADIATION PROTECTION BASELINE INSPECTION 1
IP Verification of Licensee Responses to NRC Requirement for Inventories of Materials Tracked in NSTS 2515/179 10/03/2011 10/07/2011 IP Radiological Hazard Assessment and Exposure Controls 71124.01 10/03/2011 10/07/2011 BI OL
- BIENNIAL REQUAL PROGRAM INSPECTION 2
IP Licensed Operator Requalification Program 7111111B 10/17/2011 10/21/2011
M. Schimmel 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 Robert Orlikowski at 630-829-9753 with any questions you may have regarding this letter or the inspection plan.
Sincerely,
/RA/
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 DOCUMENT NAME: G:\\Branch TSS\\ALL MOC\\midcycle 2010 to 2011\\midcycle letters\\Prairie Island 2010 MOC Letter.docx Publicly Available Non-Publicly Available Sensitive Non-Sensitive To receive a copy of this document, indicate in the concurrence box "C" = Copy without attach/encl "E" = Copy with attach/encl "N"
= No copy OFFICE RIII RIII NAME ROrlikowski:dtp SWest DATE 08/27/10 08/27/10 OFFICIAL RECORD COPY
Letter to M. Schimmel from S. West dated September 1, 2010.
SUBJECT:
MID-CYCLE PERFORMANCE REVIEW AND INSPECTION PLAN -
PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 DISTRIBUTION:
Susan Bagley RidsNRRDORlLpl3-1 RidsNRRPMPrairieIsland Resource RidsNrrDirsIpab Resource Steven Reynolds Steven Orth Jared Heck Allan Barker Carole Ariano Linda Linn DRPIII DRSIII Patricia Buckley Tammy Tomczak ROPreports Resource