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| number = ML092400145
| number = ML092400145
| issue date = 09/01/2009
| issue date = 09/01/2009
| title = 09/01/2009 Wolf Creek 2009 Midcycle Assessment
| title = Midcycle Assessment
| author name = Chamberlain D
| author name = Chamberlain D
| author affiliation = NRC/RGN-IV/DRP
| author affiliation = NRC/RGN-IV/DRP
Line 15: Line 15:


=Text=
=Text=
{{#Wiki_filter:UNITED STATESNUCLEAR REGULATORY COMMISSIONREGION IV612 EAST LAMAR BLVD, SUITE 400ARLINGTON, TEXAS 76011-4125           September 1, 2009  
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION R E GI ON I V 612 EAST LAMAR BLVD, SUITE 400 ARLINGTON, TEXAS 76011-4125 September 1, 2009 Rick A. Muench, President and Chief Executive Officer Wolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington, KS 66839  
 
Rick A. Muench, President and
 
Chief Executive Officer  
 
Wolf Creek Nuclear Operating Corporation  
 
P.O. Box 411  
 
Burlington, KS 66839  


==SUBJECT:==
==SUBJECT:==
Line 31: Line 21:


==Dear Mr. Muench:==
==Dear Mr. Muench:==
On August 4, 2009, the NRC staff completed its performance review of the Wolf Creek Generating Staion. Our technical staff reviewed performance indicators for the most recent quarter and inspection results for the period from July 1, 2008 through June 30, 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.
Plant performance for the most recent quarter at the Wolf Creek Generating Station was within the Licensee Response column of the NRC=s Action Matrix, based on all inspection findings being classified as having very low safety significance (Green) and all performance indicators indicating performance at a level requiring no additional NRC oversight (Green).
Our midcycle assessment {{letter dated|date=September 2, 2008|text=letter dated September 2, 2008}}, identified a substantive crosscutting issue in the area of human performance associated with instances of failure to have complete, accurate, and up-to-date documentation, procedures, and/or work packages within the resources component [H.2(c)]. The basis for identifying the substantive crosscutting issue was five findings, which composed a theme in this area. Our end-of-cycle assessment {{letter dated|date=March 4, 2009|text=letter dated March 4, 2009}}, sustained this substantive crosscutting issue. During that assessment period, the number of findings increased to six findings related to the theme. During a public meeting with the NRC on October 21, 2008, you informed us that you had completed a root cause analysis of your human performance issues and provided details on your Human Performance Initiative Plan and your Maintenance Work Package Quality Initiative Plan, which you were using to address human performance issues. Additionally, during a public meeting with the NRC on July 1, 2009, you further informed us of additional initiatives taken as corrective actions in accordance with your improvement plan. We have observed a decrease in the number of human performance related findings which relate to having complete, accurate, and up-to-date documentation, procedures, and/or work packages [H.2(c)]. During this assessment period, only two findings were identified with this common theme, none coming in the last half of the assessment period. As a result of your implemented corrective actions and in light of fewer human performance related findings with this common theme, this substantive crosscutting issue is closed.


On August 4, 2009, the NRC staff completed its performance review of the Wolf Creek Generating Staion. Our technical staff reviewed performance indicators for the most recent quarter and inspection results for the period from July 1, 2008 through June 30, 2009. The purpose of this letter is to inform you of our assessment of your safety performance during this
Wolf Creek Nuclear Operating Corp.
 
At the 2008 midcycle and end-of-cycle assessments, a theme for an inadequate threshold for identifying problems [P.1 (a)] was identified as part of a substantive crosscutting issue in problem identification and resolution. In our 2008 assessment letters, we stated that this theme would remain open until we determined that your corrective actions had been effective. During public meetings with the NRC on October 21, 2008, and July 1, 2009, you informed us that you had taken corrective action to improve your threshold for reporting issues. These corrective actions have resulted in an increase in the number of condition reports and work requests your staff has generated. We also noted this specific improvement by observing there was only one finding in the most recent end-of-cycle assessment and two findings in the current assessment related to the theme of failure to have an adequate threshold for identifying problems. Finally, we also have observed a declining trend in the number of NRC identified issues, from over 30 NRC identified findings in each of the previous two assessment periods to 18 in the current assessment period. Your corrective actions have shown an improving trend; therefore, this substantive crosscutting theme associated with a low enough threshold for identifying problems
period and our plans for future inspections at your facility.
[P.1 (a)] is closed.
 
At the 2008 midcycle and end-of-cycle assessments, a theme associated with the thoroughness of problem evaluation [P.1(c)] was also identified as part of a substantive crosscutting issue in problem identification and resolution based on seven and eight related findings, respectively. In both the 2008 midcycle and end-of-cycle assessment letters, we stated that this new substantive crosscutting issue would remain open until we determined that your corrective actions had been effective. During public meetings with the NRC on October 21, 2008, and July 1, 2009, you informed us that you had completed a root cause analysis for noted deficiencies related to problem identification and resolution. You also informed us that you had implemented significant changes in improving the quality of problem evaluation, including root cause evaluator training, conducting a management alignment seminar, and increasing management oversight of problem evaluation. We have noted through recent inspection efforts, including a focused baseline inspection of the residual heat removal system, that you have shown some improvement in this area; however, we did not observe sustained improvement over the entire assessment period. We continue to identify findings associated with this theme including four Green findings associated with this theme identified during this assessment period. Therefore, the substantive crosscutting theme associated with the thoroughness of problem evaluation
This performance review and enclosed inspection plan do not include security information. A
[P.1(c)] will remain open pending further demonstration of the effectiveness of your corrective actions.
 
Finally, at the 2008 midcycle and end-of-cycle assessments, a theme associated with the appropriateness of corrective actions [P.1 (d)] was also identified as part of a substantive crosscutting issue in problem identification and resolution based on seven and eight related findings, respectively. In both the 2008 midcycle and end-of-cycle assessment letter, we stated that this new substantive crosscutting issue would remain open until we determined that your corrective actions had been effective. During public meetings with the NRC on October 21, 2008 and July 1, 2009, you informed us that you had completed a root cause analysis for noted deficiencies related to problem identification and resolution and implemented corrective actions.
separate letter designated and marked as "Official Use Only -- Security Information" will include
These actions appear to have been effective, since there were only two findings related to the theme of failing to employ effective corrective actions, with none coming in the last three quarters of the assessment period. Therefore, the substantive crosscutting theme associated with the appropriateness of corrective actions [P.1 (d)] is closed.
 
The substantive crosscutting issue in problem identification and resolution will remain open, based solely on a theme associated with the thoroughness of problem evaluation [P.1(c)]. This  
the security cornerstone review and resultant inspection plan.
 
Plant performance for the most recent quarter at the Wolf Creek Generating Station was within
 
the Licensee Response column of the NRC
=s Action Matrix, based on all inspection findings being classified as having very low safety signi ficance (Green) and all performance indicators indicating performance at a level requiring no additional NRC oversight (Green). 
 
Our midcycle assessment letter dated September 2, 2008, identified a substantive crosscutting
 
issue in the area of human performance associated with instances of failure to have complete, accurate, and up-to-date documentation, procedures, and/or work packages within the
 
resources component [H.2(c)]. The basis for identifying the substantive crosscutting issue was
 
five findings, which composed a theme in this area. Our end-of-cycle assessment letter dated
 
March 4, 2009, sustained this substantive crosscutting issue. During that assessment period, the number of findings increased to six findings related to the theme. During a public meeting with the NRC on October 21, 2008, you informed us that you had completed a root cause analysis of your human performance issues and provided details on your Human Performance Initiative Plan and your Maintenance Work Package Quality Initiative Plan, which you were
 
using to address human performance issues. Additionally, during a public meeting with the
 
NRC on July 1, 2009, you further informed us of additional initiatives taken as corrective actions
 
in accordance with your improvement plan.
We have observed a decrease in the number of human performance related findings which relate to having complete, accurate, and up-to-date
 
documentation, procedures, and/or work packages [H.2(c)]. During this assessment period, only two findings were identified with this common theme, none coming in the last half of the
 
assessment period. As a result of your impl emented corrective actions and in light of fewer human performance related findings with this common theme, this substantive crosscutting
 
issue is closed.
 
Wolf Creek Nuclear Operating Corp. At the 2008 midcycle and end-of-cycle assessments, a theme for an inadequate threshold for  
 
identifying problems [P.1 (a)] was identified as part of a substantive crosscutting issue in  
 
problem identification and resolution. In our 2008 assessment letters, we stated that this theme  
 
would remain open until we determined that your corrective actions had been effective. During  
 
public meetings with the NRC on October 21, 2008, and July 1, 2009, you informed us that you  
 
had taken corrective action to improve your th reshold for reporting issues. These corrective actions have resulted in an increase in the number of condition reports and work requests your  
 
staff has generated. We also noted this specific improvement by observing there was only one  
 
finding in the most recent end-of-cycle assessment and two findings in the current assessment  
 
related to the theme of failure to have an adequate threshold for identifying problems. Finally, we also have observed a declining trend in the number of NRC identified issues, from over 30 NRC identified findings in each of the previous two assessment periods to 18 in the current assessment period. Your corrective actions hav e shown an improving trend; therefore, this substantive crosscutting theme associated with a low enough threshold for identifying problems
[P.1 (a)] is closed.  
 
At the 2008 midcycle and end-of-cycle assessments, a theme associated with the thoroughness  
 
of problem evaluation [P.1(c)] was also identified as part of a substantive crosscutting issue in  
 
problem identification and resolution based on seven and eight related findings, respectively. In  
 
both the 2008 midcycle and end-of-cycle assessment letters, we stated that this new  
 
substantive crosscutting issue would remain open until we determined that your corrective  
 
actions had been effective. During public meetings with the NRC on October 21, 2008, and July  
 
1, 2009, you informed us that you had completed a root cause analysis for noted deficiencies  
 
related to problem identification and resolution.
You also informed us that you had implemented significant changes in improving the quality of problem evaluation, including root cause evaluator training, conducting a management alignment seminar, and increasing management  
 
oversight of problem evaluation. We have noted through recent inspection efforts, including a  
 
focused baseline inspection of the residual heat removal system, that you have shown some  
 
improvement in this area; however, we did not observe sustained improvement over the entire assessment period. We continue to identify findings associated with this theme including four  
 
Green findings associated with this theme identified during this assessment period. Therefore, the substantive crosscutting theme associated with the thoroughness of problem evaluation
[P.1(c)] will remain open pending further demonstrat ion of the effectiveness of your corrective actions.
Finally, at the 2008 midcycle and end-of-cycle assessments, a theme associated with the  
 
appropriateness of corrective actions [P.1 (d)] was also identified as part of a substantive  
 
crosscutting issue in problem identification and resolution based on seven and eight related  
 
findings, respectively. In both the 2008 midcycle and end-of-cycle assessment letter, we stated  
 
that this new substantive crosscutting issue would remain open until we determined that your  
 
corrective actions had been effective. During public meetings with the NRC on October 21, 2008 and July 1, 2009, you informed us that you had completed a root cause analysis for noted  
 
deficiencies related to problem identification and resolution and implemented corrective actions.  
 
These actions appear to have been effective, since there were only two findings related to the  
 
theme of failing to employ effective corrective actions, with none coming in the last three  
 
quarters of the assessment period. Therefore, the substantive crosscutting theme associated  
 
with the appropriateness of corrective actions [P.1 (d)] is closed.  
 
The substantive crosscutting issue in problem identification and resolution will remain open, based solely on a theme associated with the thoroughness of problem evaluation [P.1(c)]. This Wolf Creek Nuclear Operating Corp. substantive crosscutting issue will remain open until we determine, through our inspections, that
 
corrective actions implemented in accordance wi th your improvement plan have resulted in improved performance in this area. Of note, th is is the third consecutive assessment with a substantive crosscutting area in problem identification and resolution with this common theme. 
 
NRC Manual Chapter 0305, "Operating Reactor Assessm ent Program," states, that "In the third consecutive assessment letter identifying the same substantive crosscutting issue with the
 
same crosscutting aspect, the regional office would typically request that the licensee perform
 
an assessment of safety culture. The regional office could conclude a safety culture
 
assessment is not warranted if the licensee has made reasonable progress in addressing the
 
issue but has not yet met the specific closure criteria for the issue."  We note that, although you
 
have not met our criteria for closing this crosscutting theme, you have made reasonable progress in addressing this issue. As such, we have concluded that a safety culture assessment is not warranted at this time. However, we do request that you schedule a public meeting to discuss your continued progress in addressing this area before our next end-of-cycle
 
assessment. We are also evaluating potential changes to the inspection program in the
 
radiation safety cornerstone. Consequently, some specific inspection procedures and the
 
inspection schedule may be revised for 2010.
 
The enclosed inspection plan details the inspections, less those related to physical protection
 
scheduled through December 31, 2010. 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 nine months of the inspection plan are tentative
 
and may be revised at the end-of-cycle review. 
 
In accordance with 10 CFR 2.390 of the NRC
=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 Avail able 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  
Wolf Creek Nuclear Operating Corp.
substantive crosscutting issue will remain open until we determine, through our inspections, that corrective actions implemented in accordance with your improvement plan have resulted in improved performance in this area. Of note, this is the third consecutive assessment with a substantive crosscutting area in problem identification and resolution with this common theme.
NRC Manual Chapter 0305, Operating Reactor Assessment Program, states, that In the third consecutive assessment letter identifying the same substantive crosscutting issue with the same crosscutting aspect, the regional office would typically request that the licensee perform an assessment of safety culture. The regional office could conclude a safety culture assessment is not warranted if the licensee has made reasonable progress in addressing the issue but has not yet met the specific closure criteria for the issue. We note that, although you have not met our criteria for closing this crosscutting theme, you have made reasonable progress in addressing this issue. As such, we have concluded that a safety culture assessment is not warranted at this time. However, we do request that you schedule a public meeting to discuss your continued progress in addressing this area before our next end-of-cycle assessment. We are also evaluating potential changes to the inspection program in the radiation safety cornerstone. Consequently, some specific inspection procedures and the inspection schedule may be revised for 2010.
The enclosed inspection plan details the inspections, less those related to physical protection scheduled through December 31, 2010. 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 nine months of the inspection plan are tentative and may be revised at the end-of-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 me at 817-860-8141 with any questions you may have regarding this letter or the inspection plan.
Sincerely,
/RA/
Dwight D. Chamberlain, Director Division of Reactor Projects Docket: 50-482 License: NPF-42


discuss the change as soon as possible. Please contact me at 817-860-8141 with any
Wolf Creek Nuclear Operating Corp.  
 
questions you may have regarding this letter or the inspection plan.
 
Sincerely,          /RA/  Dwight D. Chamberlain, Director Division of Reactor Projects Docket:  50-482
 
License:  NPF-42
 
Wolf Creek Nuclear Operating Corp.  


==Enclosure:==
==Enclosure:==
 
Wolf Creek Inspection Activity Plan cc w/
Wolf Creek Inspection Activity Plan  
 
cc w/


==Enclosure:==
==Enclosure:==
Vice President Operations/Plant Manager Wolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington, KS 66839 Jay Silberg, Esq.
Pillsbury Winthrop Shaw Pittman LLP 2300 N Street, NW Washington, DC 20037 Supervisor Licensing Wolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington, KS 66839 Chief Engineer Utilities Division Kansas Corporation Commission 1500 SW Arrowhead Road Topeka, KS 66604-4027 Office of the Governor State of Kansas Topeka, KS 66612-1590 Attorney General 120 S.W. 10th Avenue, 2nd Floor Topeka, KS 66612-1597 County Clerk Coffey County Courthouse 110 South 6th Street Burlington, KS 66839 Chief, Radiation and Asbestos Control Section Bureau of Air and Radiation Kansas Department of Health and Environment 1000 SW Jackson, Suite 310 Topeka, KS 66612-1366 Chief, Technological Hazards Branch FEMA, Region VII 9221 Ward Parkway Suite 300 Kansas City, MO 64114-3372


Vice President Operations/Plant Manager
Wolf Creek Nuclear Operating Corp.
 
5 Electronic distribution by RIV:
Wolf Creek Nuclear Operating Corporation
Regional Administrator (Elmo.Collins@nrc.gov)
 
Deputy Regional Administrator (Chuck.Casto@nrc.gov)
P.O. Box 411
DRP Director (Dwight.Chamberlain@nrc.gov)
 
DRP Deputy Director (Anton.Vegel@nrc.goV)
Burlington, KS  66839
DRP Director (Roy.Caniano@nrc.gov)
 
DRP Deputy Director (Troy.Pruett@nrc.gov)
Jay Silberg, Esq.
Branch Chief, DRP (Vincent.Gaddy@nrc.gov)
 
Senior Project Engineer, DRP (Rick.Deese@nrc.gov)
Pillsbury Winthrop Shaw Pittman LLP
Senior Resident Inspector (Chris.Long@nrc.gov)
 
Resident Inspector (Charles.Peabody@nrc.gov)
2300 N Street, NW Washington, DC  20037
 
Supervisor Licensing
 
Wolf Creek Nuclear Operating Corporation
 
P.O. Box 411
 
Burlington, KS  66839
 
Chief Engineer
 
Utilities Division
 
Kansas Corporation Commission
 
1500 SW Arrowhead Road
 
Topeka, KS  66604-4027
 
Office of the Governor
 
State of Kansas
 
Topeka, KS  66612-1590 Attorney General
 
120 S.W. 10th Avenue, 2nd Floor
 
Topeka, KS  66612-1597
 
County Clerk Coffey County Courthouse 110 South 6th Street
 
Burlington, KS  66839
 
Chief, Radiation and Asbestos
 
Control Section
 
Bureau of Air and Radiation
 
Kansas Department of Health and
 
Environment
 
1000 SW Jackson, Suite 310
 
Topeka, KS  66612-1366
 
Chief, Technological Hazards
 
Branch
 
FEMA, Region VII
 
9221 Ward Parkway
 
Suite 300
 
Kansas City, MO  64114-3372
 
Wolf Creek Nuclear Operating Corp. 5 Electronic distribution by RIV:  
 
Regional Administrator (Elmo.Collins@nrc.gov)  
 
Deputy Regional Administrator (Chuck.Casto@nrc.gov)  
 
DRP Director (Dwight.Chamberlain@nrc.gov)  
 
DRP Deputy Director (Anton.Vegel@nrc.goV)  
 
DRP Director (Roy.Caniano@nrc.gov)  
 
DRP Deputy Director (Troy.Pruett@nrc.gov)  
 
Branch Chief, DRP (Vincent.Gaddy@nrc.gov)  
 
Senior Project Engineer, DRP (Rick.Deese@nrc.gov)  
 
Senior Resident Inspector (Chris.Long@nrc.gov)  
 
Resident Inspector (Charles.Peabody@nrc.gov)  
 
Team Leader, DRP/TSS (Chuck.Paulk@nrc.gov)
Team Leader, DRP/TSS (Chuck.Paulk@nrc.gov)
RITS Coordinator (Marisa.Herrera@nrc.gov) Public Affairs Officer (Victor.Dricks@nrc.gov)  
RITS Coordinator (Marisa.Herrera@nrc.gov)
Public Affairs Officer (Victor.Dricks@nrc.gov)
Regional State Liaison Officer (Bill.Maier@nrc.gov)
RA Secretary (Lucy.Owen@nrc.gov)
DRA Secretary (Judy.Kilcrease@nrc.gov)
Branch Chief, DRS/EB1 (Thomas.Farnholtz@nrc.gov)
Branch Chief, DRS/EB2 (Neil.OKeefe@nrc.gov)
Branch Chief, DRS/PSB1 (Michael.Shannon@nrc.gov)
Branch Chief, DRS/PSB2 (Greg.Werner@nrc.gov)
Branch Chief, DRS/OB (Ryan.Lantz@nrc.gov)
OEDO RIV Coordinator, Primary (Leigh.Trocine@nrc.gov)
OEDO, TRPS (Tamara.Bloomer@nrc.gov)
Deputy Director, DIRS, NRR (Frederick.Brown@nrc.gov)
Director, DORL, NRR (Joseph Giitter@nrc.gov)
Deputy Director, DORL, NRR (Timothy.McGinty@nrc.gov)
Chief, PLB IV, DORL, NRR (Thomas.Hiltz@nrc.gov)
NRR Project Manager (Balwant.Singal@nrc.gov)
RidsNrrDirslpab (Resource@nrc.gov)
Congressional Affairs Officer (Jenny.Weil@nrc.gov) mortensengk@INPO.org ROP Reports File located: R:\\EOC and Midcycle\\Midcycle Assessment Letters\\2009\\WC.doc SUNSI Rev Compl.
Yes No ADAMS Yes No Reviewer Initials VGG Publicly Avail Yes No Sensitive Yes No Sens. Type Initials VGG RIV:SPE/DRP/PBB C:DRP/PBB D:DRS D:DRP RWDeese VGGaddy RJCaniano DDChamberlain
/RA/
/RA/
/RA/
/RA/
8/18/09 8/19/09 8/20/09 8/24/09 OFFICIAL RECORD COPY T=Telephone E=E-mail F=Fax


Regional State Liaison Officer (Bill.Maier@nrc.gov)
Wolf Creek Nuclear Operating Corp.
6


RA Secretary (Lucy.Owen@nrc.gov)
Inspection / Activity Plan Page 1 of 2 08/17/2009 14:27:55 Report 22 09/01/2009 - 12/31/2010 Unit Number Planned Dates Start End Inspection Activity Title No. of Staff on Site Wolf Creek EXAM
 
- INITIAL EXAM 3
DRA Secretary (Judy.Kilcrease@nrc.gov)  
1 INITIAL EXAM-WC (8/2009)
 
X02419 08/31/2009 09/04/2009 EB1-08
Branch Chief, DRS/EB1 (Thomas.Farnholtz@nrc.gov)
- INSERVICE INSPECTION 3
 
1 IP Reactor Coolant System Dissimiliar Metal Butt Welds 2515/172 10/10/2009 10/30/2009 1
Branch Chief, DRS/EB2 (Neil.OKeefe@nrc.gov)
IP Inservice Inspection Activities - PWR 7111108P 10/10/2009 10/30/2009 RP-ORS3
 
- OCCUPATIONAL RADIATION SAFETY - ALARA 1
Branch Chief, DRS/PSB1 (Michael.Shannon@nrc.gov)
1 IP Access Control to Radiologically Significant Areas 7112101 10/19/2009 10/23/2009 1
 
IP ALARA Planning and Controls 7112102 10/19/2009 10/23/2009 1
Branch Chief, DRS/PSB2 (Greg.Werner@nrc.gov)
IP Performance Indicator Verification 71151 10/19/2009 10/23/2009 RP-ORS4
 
- OCCUPATIONAL RADIATION SAFETY - ACCESS 1
Branch Chief, DRS/OB (Ryan.Lantz@nrc.gov)
1 IP Access Control to Radiologically Significant Areas 7112101 10/19/2009 10/23/2009 1
 
IP ALARA Planning and Controls 7112102 10/19/2009 10/23/2009 1
OEDO RIV Coordinator, Primary (Leigh.Trocine@nrc.gov)
IP Performance Indicator Verification 71151 10/19/2009 10/23/2009 RP-ORS1
 
- OCCUPATIONAL RADIATION SAFETY - ALARA 1
OEDO, TRPS (Tamara.Bloomer@nrc.gov)
1 IP Access Control to Radiologically Significant Areas 7112101 03/15/2010 03/19/2010 1
 
IP ALARA Planning and Controls 7112102 03/15/2010 03/19/2010 1
Deputy Director, DIRS, NRR (Frederick.Brown@nrc.gov)
IP Occupational Exposure Control Effectiveness 71151-OR01 03/15/2010 03/19/2010 1
IP RETS/ODCM Radiological Effluent 71151-PR01 03/15/2010 03/19/2010 EP-1
- BIENNIAL EP PROGRAM INSPECTION 1
1 IP Alert and Notification System Testing 7111402 04/12/2010 04/16/2010 1
IP Emergency Response Organization Augmentation Testing 7111403 04/12/2010 04/16/2010 1
IP Emergency Action Level and Emergency Plan Changes 7111404 04/12/2010 04/16/2010 1
IP Correction of Emergency Preparedness Weaknesses and Deficiencies 7111405 04/12/2010 04/16/2010 1
IP Drill/Exercise Performance 71151-EP01 04/12/2010 04/16/2010 1
IP ERO Drill Participation 71151-EP02 04/12/2010 04/16/2010 1
IP Alert & Notification System 71151-EP03 04/12/2010 04/16/2010 RP-ORS1
- OCCUPATIONAL RADIATION SAFETY-ACRSA 1
1 IP Access Control to Radiologically Significant Areas 7112101 05/10/2010 05/14/2010 1
IP ALARA Planning and Controls 7112102 05/10/2010 05/14/2010 1
IP Performance Indicator Verification 71151 05/10/2010 05/14/2010 PSB2-52B
- BIENNIAL PI&R 4
1 IP Identification and Resolution of Problems 71152B 07/12/2010 07/16/2010 1
IP Identification and Resolution of Problems 71152B 07/26/2010 07/30/2010 EB1-21
- COMPONENT DESIGN BASIS INSPECTION 6
1 IP Component Design Bases Inspection 7111121 09/07/2010 09/10/2010 This report does not include INPO and OUTAGE activities.
This report shows only on-site and announced inspection procedures.


Director, DORL, NRR (Joseph Giitter@nrc.gov)
Inspection / Activity Plan Page 2 of 2 08/17/2009 14:27:55 Report 22 09/01/2009 - 12/31/2010 Unit Number Planned Dates Start End Inspection Activity Title No. of Staff on Site Wolf Creek EB1-21
 
- COMPONENT DESIGN BASIS INSPECTION 6
Deputy Director, DORL, NRR (Timothy.McGinty@nrc.gov)
1 IP Component Design Bases Inspection 7111121 09/20/2010 10/01/2010 BRQ
 
- OPERATOR REQUAL INSP 2
Chief, PLB IV, DORL, NRR (Thomas.Hiltz@nrc.gov)
1 IP Licensed Operator Requalification Program 7111111B 10/04/2010 10/08/2010 RP TEAM
 
- RADIATION SAFETY TEAM INSPECTION 4
NRR Project Manager (Balwant.Singal@nrc.gov)
1 IP Radiation Monitoring Instrumentation and Protective Equipment 7112103 10/18/2010 10/22/2010 1
 
IP Radioactive Gaseous and Liquid Effluent Treatment and Monitoring Systems 7112201 10/18/2010 10/22/2010 1
RidsNrrDirslpab (Resource@nrc.gov)
IP Radioactive Material Processing and Transportation 7112202 10/18/2010 10/22/2010 1
 
IP Radiological Environmental Monitoring Program (REMP) And Radioactive Material Control Program 7112203 10/18/2010 10/22/2010 1
Congressional Affairs Officer (Jenny.Weil@nrc.gov) mortensengk@INPO.org ROP Reports
IP Material Control and Accounting (MC&A) 7113011 10/18/2010 10/22/2010 EB2-07T
 
- TRIENNIAL HEAT SINK PERFORMANCE 1
File located:  R:\EOC and Midcycle\Midcycle Assessment Letters\2009\WC.doc SUNSI Rev Compl. Yes  No ADAMS  Yes  No Reviewer Initials VGG Publicly Avail  Yes  No Sensitive  Yes  No Sens. Type Initials VGG RIV:SPE/DRP/PBB C:DRP/PBB D:DRS D:DRP  RWDeese VGGaddy RJCaniano DDChamberlain
1 IP Heat Sink Performance 7111107T 10/25/2010 10/29/2010 EXAM
/RA/ /RA/ /RA/ /RA/  8/18/09 8/19/09 8/20/09 8/24/09  OFFICIAL RECORD COPY    T=Telephone          E=E-mail        F=Fax Wolf Creek Nuclear Operating Corp. 6
- INITIAL EXAM 4
 
1 INITIAL EXAM -WC (11/2010)
Inspection / Activity Plan Page 1 of 2 08/17/2009 14:27:55 Report 22 09/01/2009
X02451 11/08/2010 11/12/2010 1
-12/31/2010 Unit Number Planned Dates Start           End Inspection Activity Title No. of Staff on Site Wolf Creek EXAM-INITIAL EXAM 3 1    INITIAL EXAM-WC (8/2009)
INITIAL EXAM -WC (11/2010)
X02419 08/31/2009 09/04/2009 EB1-08-INSERVICE INSPECTION 3 1    IP Reactor Coolant System Dissimiliar Metal Butt Welds 2515/172 10/10/2009 10/30/2009 1    IP Inservice Inspection Activities - PWR 7111108P 10/10/2009 10/30/2009 RP-ORS3-OCCUPATIONAL RADIATION SAFETY - ALARA 1 1    IP A ccess Control to Radiologically Significant Areas 7112101 10/19/2009 10/23/2009 1    IP A LARA Planning and Controls 7112102 10/19/2009 10/23/2009 1    IP Performance Indicator Verification 71151 10/19/2009 10/23/2009 RP-ORS4-OCCUPATIONAL RADIATION SAFETY - ACCESS 1 1    IP A ccess Control to Radiologically Significant Areas 7112101 10/19/2009 10/23/2009 1    IP A LARA Planning and Controls 7112102 10/19/2009 10/23/2009 1    IP Performance Indicator Verification 71151 10/19/2009 10/23/2009 RP-ORS1-OCCUPATIONAL RADIATION SAFETY - ALARA 1 1    IP A ccess Control to Radiologically Significant Areas 7112101 03/15/2010 03/19/2010 1    IP A LARA Planning and Controls 7112102 03/15/2010 03/19/2010 1    IP Occupational Exposure Control Effectiveness 71151-OR01 03/15/2010 03/19/2010 1    IP RETS/ODCM Radiological Effluent 71151-PR01 03/15/2010 03/19/2010 EP-1-BIENNIAL EP PROGRAM INSPECTION 1 1    IP A lert and Notification System Testing 7111402 04/12/2010 04/16/2010 1    IP Emergency Response Organization Augmentation Testing 7111403 04/12/2010 04/16/2010 1    IP Emergency Action Level and Emergency Plan Changes 7111404 04/12/2010 04/16/2010 1    IP Correction of Emergency Preparedness Weaknesses and Deficiencies 7111405 04/12/2010 04/16/2010 1    IP Drill/Exercise Performance 71151-EP01 04/12/2010 04/16/2010 1    IP ERO Drill Participation 71151-EP02 04/12/2010 04/16/2010 1    IP A lert & Notification System 71151-EP03 04/12/2010 04/16/2010 RP-ORS1-OCCUPATIONAL RADIATION SAFETY-ACRSA 1 1    IP A ccess Control to Radiologically Significant Areas 7112101 05/10/2010 05/14/2010 1    IP A LARA Planning and Controls 7112102 05/10/2010 05/14/2010 1    IP Performance Indicator Verification 71151 05/10/2010 05/14/2010 PSB2-52B-BIENNIAL PI&R 4 1    IP Identification and Resolution of Problems 71152B 07/12/2010 07/16/2010 1    IP Identification and Resolution of Problems 71152B 07/26/2010 07/30/2010 EB1-21-COMPONENT DESIGN BASIS INSPECTION 6 1    IP Component Design Bases Inspection 7111121 09/07/2010 09/10/2010 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 08/17/2009 14:27:55 Report 22 09/01/2009
-12/31/2010 Unit Number Planned Dates Start          End Inspection Activity Title No. of Staff on Site Wolf Creek EB1-21-COMPONENT DESIGN BASIS INSPECTION 6 1     IP Component Design Bases Inspection 7111121 09/20/2010 10/01/2010 BRQ-OPERATOR REQUAL INSP 2 1     IP Licensed Operator Requalification Program 7111111B 10/04/2010 10/08/2010 RP TEAM-RADIATION SAFETY TEAM INSPECTION 4 1     IP Radiation Monitoring Instrumentation and Protective Equipment 7112103 10/18/2010 10/22/2010 1     IP Radioactive Gaseous and Liquid Effluent Treatment and Monitoring Systems 7112201 10/18/2010 10/22/2010 1     IP Radioactive Material Processing and Transportation 7112202 10/18/2010 10/22/2010 1     IP Radiological Environmental Monitoring Program (REMP) And Radioactive Material Control Program 7112203 10/18/2010 10/22/2010 1     IP Material Control and Accounting (MC&A) 7113011 10/18/2010 10/22/2010 EB2-07T-TRIENNIAL HEAT SINK PERFORMANCE 1 1     IP Heat Sink Performance 7111107T 10/25/2010 10/29/2010 EXAM-INITIAL EXAM 4 1     INITIAL EXAM -WC (11/2010)
X02451 11/08/2010 11/12/2010 1     INITIAL EXAM -WC (11/2010)
X02451 12/06/2010 12/17/2010 This report does not include INPO and OUTAGE activities.
X02451 12/06/2010 12/17/2010 This report does not include INPO and OUTAGE activities.
This report shows only on-site and announced inspection procedures.}}
This report shows only on-site and announced inspection procedures.}}

Latest revision as of 09:37, 14 January 2025

Midcycle Assessment
ML092400145
Person / Time
Site: Wolf Creek Wolf Creek Nuclear Operating Corporation icon.png
Issue date: 09/01/2009
From: Chamberlain D
NRC/RGN-IV/DRP
To: Muench R
Wolf Creek
References
Download: ML092400145 (7)
v • d • e


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION R E GI ON I V 612 EAST LAMAR BLVD, SUITE 400 ARLINGTON, TEXAS 76011-4125 September 1, 2009 Rick A. Muench, President and Chief Executive Officer Wolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington, KS 66839

SUBJECT:

MIDCYCLE PERFORMANCE REVIEW AND INSPECTION PLAN - WOLF CREEK GENERATING STATION

Dear Mr. Muench:

On August 4, 2009, the NRC staff completed its performance review of the Wolf Creek Generating Staion. Our technical staff reviewed performance indicators for the most recent quarter and inspection results for the period from July 1, 2008 through June 30, 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.

Plant performance for the most recent quarter at the Wolf Creek Generating Station was within the Licensee Response column of the NRC=s Action Matrix, based on all inspection findings being classified as having very low safety significance (Green) and all performance indicators indicating performance at a level requiring no additional NRC oversight (Green).

Our midcycle assessment letter dated September 2, 2008, identified a substantive crosscutting issue in the area of human performance associated with instances of failure to have complete, accurate, and up-to-date documentation, procedures, and/or work packages within the resources component H.2(c). The basis for identifying the substantive crosscutting issue was five findings, which composed a theme in this area. Our end-of-cycle assessment letter dated March 4, 2009, sustained this substantive crosscutting issue. During that assessment period, the number of findings increased to six findings related to the theme. During a public meeting with the NRC on October 21, 2008, you informed us that you had completed a root cause analysis of your human performance issues and provided details on your Human Performance Initiative Plan and your Maintenance Work Package Quality Initiative Plan, which you were using to address human performance issues. Additionally, during a public meeting with the NRC on July 1, 2009, you further informed us of additional initiatives taken as corrective actions in accordance with your improvement plan. We have observed a decrease in the number of human performance related findings which relate to having complete, accurate, and up-to-date documentation, procedures, and/or work packages H.2(c). During this assessment period, only two findings were identified with this common theme, none coming in the last half of the assessment period. As a result of your implemented corrective actions and in light of fewer human performance related findings with this common theme, this substantive crosscutting issue is closed.

Wolf Creek Nuclear Operating Corp.

At the 2008 midcycle and end-of-cycle assessments, a theme for an inadequate threshold for identifying problems [P.1 (a)] was identified as part of a substantive crosscutting issue in problem identification and resolution. In our 2008 assessment letters, we stated that this theme would remain open until we determined that your corrective actions had been effective. During public meetings with the NRC on October 21, 2008, and July 1, 2009, you informed us that you had taken corrective action to improve your threshold for reporting issues. These corrective actions have resulted in an increase in the number of condition reports and work requests your staff has generated. We also noted this specific improvement by observing there was only one finding in the most recent end-of-cycle assessment and two findings in the current assessment related to the theme of failure to have an adequate threshold for identifying problems. Finally, we also have observed a declining trend in the number of NRC identified issues, from over 30 NRC identified findings in each of the previous two assessment periods to 18 in the current assessment period. Your corrective actions have shown an improving trend; therefore, this substantive crosscutting theme associated with a low enough threshold for identifying problems

[P.1 (a)] is closed.

At the 2008 midcycle and end-of-cycle assessments, a theme associated with the thoroughness of problem evaluation P.1(c) was also identified as part of a substantive crosscutting issue in problem identification and resolution based on seven and eight related findings, respectively. In both the 2008 midcycle and end-of-cycle assessment letters, we stated that this new substantive crosscutting issue would remain open until we determined that your corrective actions had been effective. During public meetings with the NRC on October 21, 2008, and July 1, 2009, you informed us that you had completed a root cause analysis for noted deficiencies related to problem identification and resolution. You also informed us that you had implemented significant changes in improving the quality of problem evaluation, including root cause evaluator training, conducting a management alignment seminar, and increasing management oversight of problem evaluation. We have noted through recent inspection efforts, including a focused baseline inspection of the residual heat removal system, that you have shown some improvement in this area; however, we did not observe sustained improvement over the entire assessment period. We continue to identify findings associated with this theme including four Green findings associated with this theme identified during this assessment period. Therefore, the substantive crosscutting theme associated with the thoroughness of problem evaluation

P.1(c) will remain open pending further demonstration of the effectiveness of your corrective actions.

Finally, at the 2008 midcycle and end-of-cycle assessments, a theme associated with the appropriateness of corrective actions [P.1 (d)] was also identified as part of a substantive crosscutting issue in problem identification and resolution based on seven and eight related findings, respectively. In both the 2008 midcycle and end-of-cycle assessment letter, we stated that this new substantive crosscutting issue would remain open until we determined that your corrective actions had been effective. During public meetings with the NRC on October 21, 2008 and July 1, 2009, you informed us that you had completed a root cause analysis for noted deficiencies related to problem identification and resolution and implemented corrective actions.

These actions appear to have been effective, since there were only two findings related to the theme of failing to employ effective corrective actions, with none coming in the last three quarters of the assessment period. Therefore, the substantive crosscutting theme associated with the appropriateness of corrective actions [P.1 (d)] is closed.

The substantive crosscutting issue in problem identification and resolution will remain open, based solely on a theme associated with the thoroughness of problem evaluation P.1(c). This

Wolf Creek Nuclear Operating Corp.

substantive crosscutting issue will remain open until we determine, through our inspections, that corrective actions implemented in accordance with your improvement plan have resulted in improved performance in this area. Of note, this is the third consecutive assessment with a substantive crosscutting area in problem identification and resolution with this common theme.

NRC Manual Chapter 0305, Operating Reactor Assessment Program, states, that In the third consecutive assessment letter identifying the same substantive crosscutting issue with the same crosscutting aspect, the regional office would typically request that the licensee perform an assessment of safety culture. The regional office could conclude a safety culture assessment is not warranted if the licensee has made reasonable progress in addressing the issue but has not yet met the specific closure criteria for the issue. We note that, although you have not met our criteria for closing this crosscutting theme, you have made reasonable progress in addressing this issue. As such, we have concluded that a safety culture assessment is not warranted at this time. However, we do request that you schedule a public meeting to discuss your continued progress in addressing this area before our next end-of-cycle assessment. We are also evaluating potential changes to the inspection program in the radiation safety cornerstone. Consequently, some specific inspection procedures and the inspection schedule may be revised for 2010.

The enclosed inspection plan details the inspections, less those related to physical protection scheduled through December 31, 2010. 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 nine months of the inspection plan are tentative and may be revised at the end-of-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 me at 817-860-8141 with any questions you may have regarding this letter or the inspection plan.

Sincerely,

/RA/

Dwight D. Chamberlain, Director Division of Reactor Projects Docket: 50-482 License: NPF-42

Wolf Creek Nuclear Operating Corp.

Enclosure:

Wolf Creek Inspection Activity Plan cc w/

Enclosure:

Vice President Operations/Plant Manager Wolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington, KS 66839 Jay Silberg, Esq.

Pillsbury Winthrop Shaw Pittman LLP 2300 N Street, NW Washington, DC 20037 Supervisor Licensing Wolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington, KS 66839 Chief Engineer Utilities Division Kansas Corporation Commission 1500 SW Arrowhead Road Topeka, KS 66604-4027 Office of the Governor State of Kansas Topeka, KS 66612-1590 Attorney General 120 S.W. 10th Avenue, 2nd Floor Topeka, KS 66612-1597 County Clerk Coffey County Courthouse 110 South 6th Street Burlington, KS 66839 Chief, Radiation and Asbestos Control Section Bureau of Air and Radiation Kansas Department of Health and Environment 1000 SW Jackson, Suite 310 Topeka, KS 66612-1366 Chief, Technological Hazards Branch FEMA, Region VII 9221 Ward Parkway Suite 300 Kansas City, MO 64114-3372

Wolf Creek Nuclear Operating Corp.

5 Electronic distribution by RIV:

Regional Administrator (Elmo.Collins@nrc.gov)

Deputy Regional Administrator (Chuck.Casto@nrc.gov)

DRP Director (Dwight.Chamberlain@nrc.gov)

DRP Deputy Director (Anton.Vegel@nrc.goV)

DRP Director (Roy.Caniano@nrc.gov)

DRP Deputy Director (Troy.Pruett@nrc.gov)

Branch Chief, DRP (Vincent.Gaddy@nrc.gov)

Senior Project Engineer, DRP (Rick.Deese@nrc.gov)

Senior Resident Inspector (Chris.Long@nrc.gov)

Resident Inspector (Charles.Peabody@nrc.gov)

Team Leader, DRP/TSS (Chuck.Paulk@nrc.gov)

RITS Coordinator (Marisa.Herrera@nrc.gov)

Public Affairs Officer (Victor.Dricks@nrc.gov)

Regional State Liaison Officer (Bill.Maier@nrc.gov)

RA Secretary (Lucy.Owen@nrc.gov)

DRA Secretary (Judy.Kilcrease@nrc.gov)

Branch Chief, DRS/EB1 (Thomas.Farnholtz@nrc.gov)

Branch Chief, DRS/EB2 (Neil.OKeefe@nrc.gov)

Branch Chief, DRS/PSB1 (Michael.Shannon@nrc.gov)

Branch Chief, DRS/PSB2 (Greg.Werner@nrc.gov)

Branch Chief, DRS/OB (Ryan.Lantz@nrc.gov)

OEDO RIV Coordinator, Primary (Leigh.Trocine@nrc.gov)

OEDO, TRPS (Tamara.Bloomer@nrc.gov)

Deputy Director, DIRS, NRR (Frederick.Brown@nrc.gov)

Director, DORL, NRR (Joseph Giitter@nrc.gov)

Deputy Director, DORL, NRR (Timothy.McGinty@nrc.gov)

Chief, PLB IV, DORL, NRR (Thomas.Hiltz@nrc.gov)

NRR Project Manager (Balwant.Singal@nrc.gov)

RidsNrrDirslpab (Resource@nrc.gov)

Congressional Affairs Officer (Jenny.Weil@nrc.gov) mortensengk@INPO.org ROP Reports File located: R:\\EOC and Midcycle\\Midcycle Assessment Letters\\2009\\WC.doc SUNSI Rev Compl.

Yes No ADAMS Yes No Reviewer Initials VGG Publicly Avail Yes No Sensitive Yes No Sens. Type Initials VGG RIV:SPE/DRP/PBB C:DRP/PBB D:DRS D:DRP RWDeese VGGaddy RJCaniano DDChamberlain

/RA/

/RA/

/RA/

/RA/

8/18/09 8/19/09 8/20/09 8/24/09 OFFICIAL RECORD COPY T=Telephone E=E-mail F=Fax

Wolf Creek Nuclear Operating Corp.

6

Inspection / Activity Plan Page 1 of 2 08/17/2009 14:27:55 Report 22 09/01/2009 - 12/31/2010 Unit Number Planned Dates Start End Inspection Activity Title No. of Staff on Site Wolf Creek EXAM

- INITIAL EXAM 3

1 INITIAL EXAM-WC (8/2009)

X02419 08/31/2009 09/04/2009 EB1-08

- INSERVICE INSPECTION 3

1 IP Reactor Coolant System Dissimiliar Metal Butt Welds 2515/172 10/10/2009 10/30/2009 1

IP Inservice Inspection Activities - PWR 7111108P 10/10/2009 10/30/2009 RP-ORS3

- OCCUPATIONAL RADIATION SAFETY - ALARA 1

1 IP Access Control to Radiologically Significant Areas 7112101 10/19/2009 10/23/2009 1

IP ALARA Planning and Controls 7112102 10/19/2009 10/23/2009 1

IP Performance Indicator Verification 71151 10/19/2009 10/23/2009 RP-ORS4

- OCCUPATIONAL RADIATION SAFETY - ACCESS 1

1 IP Access Control to Radiologically Significant Areas 7112101 10/19/2009 10/23/2009 1

IP ALARA Planning and Controls 7112102 10/19/2009 10/23/2009 1

IP Performance Indicator Verification 71151 10/19/2009 10/23/2009 RP-ORS1

- OCCUPATIONAL RADIATION SAFETY - ALARA 1

1 IP Access Control to Radiologically Significant Areas 7112101 03/15/2010 03/19/2010 1

IP ALARA Planning and Controls 7112102 03/15/2010 03/19/2010 1

IP Occupational Exposure Control Effectiveness 71151-OR01 03/15/2010 03/19/2010 1

IP RETS/ODCM Radiological Effluent 71151-PR01 03/15/2010 03/19/2010 EP-1

- BIENNIAL EP PROGRAM INSPECTION 1

1 IP Alert and Notification System Testing 7111402 04/12/2010 04/16/2010 1

IP Emergency Response Organization Augmentation Testing 7111403 04/12/2010 04/16/2010 1

IP Emergency Action Level and Emergency Plan Changes 7111404 04/12/2010 04/16/2010 1

IP Correction of Emergency Preparedness Weaknesses and Deficiencies 7111405 04/12/2010 04/16/2010 1

IP Drill/Exercise Performance 71151-EP01 04/12/2010 04/16/2010 1

IP ERO Drill Participation 71151-EP02 04/12/2010 04/16/2010 1

IP Alert & Notification System 71151-EP03 04/12/2010 04/16/2010 RP-ORS1

- OCCUPATIONAL RADIATION SAFETY-ACRSA 1

1 IP Access Control to Radiologically Significant Areas 7112101 05/10/2010 05/14/2010 1

IP ALARA Planning and Controls 7112102 05/10/2010 05/14/2010 1

IP Performance Indicator Verification 71151 05/10/2010 05/14/2010 PSB2-52B

- BIENNIAL PI&R 4

1 IP Identification and Resolution of Problems 71152B 07/12/2010 07/16/2010 1

IP Identification and Resolution of Problems 71152B 07/26/2010 07/30/2010 EB1-21

- COMPONENT DESIGN BASIS INSPECTION 6

1 IP Component Design Bases Inspection 7111121 09/07/2010 09/10/2010 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 08/17/2009 14:27:55 Report 22 09/01/2009 - 12/31/2010 Unit Number Planned Dates Start End Inspection Activity Title No. of Staff on Site Wolf Creek EB1-21

- COMPONENT DESIGN BASIS INSPECTION 6

1 IP Component Design Bases Inspection 7111121 09/20/2010 10/01/2010 BRQ

- OPERATOR REQUAL INSP 2

1 IP Licensed Operator Requalification Program 7111111B 10/04/2010 10/08/2010 RP TEAM

- RADIATION SAFETY TEAM INSPECTION 4

1 IP Radiation Monitoring Instrumentation and Protective Equipment 7112103 10/18/2010 10/22/2010 1

IP Radioactive Gaseous and Liquid Effluent Treatment and Monitoring Systems 7112201 10/18/2010 10/22/2010 1

IP Radioactive Material Processing and Transportation 7112202 10/18/2010 10/22/2010 1

IP Radiological Environmental Monitoring Program (REMP) And Radioactive Material Control Program 7112203 10/18/2010 10/22/2010 1

IP Material Control and Accounting (MC&A) 7113011 10/18/2010 10/22/2010 EB2-07T

- TRIENNIAL HEAT SINK PERFORMANCE 1

1 IP Heat Sink Performance 7111107T 10/25/2010 10/29/2010 EXAM

- INITIAL EXAM 4

1 INITIAL EXAM -WC (11/2010)

X02451 11/08/2010 11/12/2010 1

INITIAL EXAM -WC (11/2010)

X02451 12/06/2010 12/17/2010 This report does not include INPO and OUTAGE activities.

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

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