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| number = ML090630773
| number = ML090630773
| issue date = 03/04/2009
| issue date = 03/04/2009
| title = Wolf Creek Generating Station - Annual Assessment Letter and Inspection Plan 2008 (NRC Inspection Report 05000482-09-001)
| title = Annual Assessment Letter and Inspection Plan 2008 (NRC Inspection Report 05000482-09-001)
| author name = Chamberlain D D
| author name = Chamberlain D
| author affiliation = NRC/RGN-IV/DRP
| author affiliation = NRC/RGN-IV/DRP
| addressee name = Muench R A
| addressee name = Muench R
| addressee affiliation = Wolf Creek Nuclear Operating Corp
| addressee affiliation = Wolf Creek Nuclear Operating Corp
| docket = 05000482
| docket = 05000482
Line 18: Line 18:


=Text=
=Text=
{{#Wiki_filter:
{{#Wiki_filter:UNITED STATES NU C LE AR RE G ULATO RY C O M M I S S I O N rch 4, 2009
[[Issue date::March 4, 2009]]


Rick A. Muench, President and Chief Executive Officer
==SUBJECT:==
 
ANNUAL ASSESSMENT LETTER - WOLF CREEK GENERATING STATION (NRC INSPECTION REPORT 05000482/2009001)
Wolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington, KS 66839
 
SUBJECT: ANNUAL ASSESSMENT LETTER - WOLF CREEK GENERATING STATION (NRC INSPECTION REPORT 05000482/2009001)


==Dear Mr. Muench:==
==Dear Mr. Muench:==
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This performance review and enclosed inspection plan do not include security information. A separate letter designated and marked as "Official Use Only - Security-Related 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-Related Information" will include the security cornerstone review and resultant inspection plan.


Overall, the Wolf Creek Generating Station operated in a manner that preserved public health and safety and fully met all cornerstone objectives. Plant performance for the most recent quarter, as well as for the first three quarters of the assessment cycle, was within the Licensee Response column of the NRC
Overall, the Wolf Creek Generating Station operated in a manner that preserved public health and safety and fully met all cornerstone objectives. Plant performance for the most recent quarter, as well as for the first three quarters of the assessment cycle, 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). Therefore, we plan to conduct reactor oversight process baseline inspections at your facility.
=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). Therefore, we plan to conduct reactor oversight process baseline inspections at your facility.
 
Our mid-cycle assessment letter dated September 2, 2008, identified a substantive cross-cutting 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 cross-cutting issue at that time was five findings which composed a theme. During this assessment period, the number of findings increased to six findings related to the theme of failure to have complete, accurate, and up-to-date documentation, procedures, and/or work packages. These findings affected the Initiating Events, Mitigating Systems, and the Pubic Radiation Safety cornerstones. Examples include: an inadequate surveillance procedure that did not include all emergency core cooling vent valves, a procedure that did not include acceptance criteria for gaps in the containment sump, an inadequate procedure that resulted in the loss of all condensate pumps and a subsequent reactor trip, and an inadequate switchyard maintenance procedure that lead to a loss of all offsite power. During a public meeting with the NRC on October 21, 2008, you Wolf Creek Nuclear Operating Corp - 2 - informed us that you had recently completed a root cause analysis of your human performance issues. You also 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. The actions that you implemented have not yet proven effective in substantially mitigating this cross-cutting theme as evidenced by the number of existing findings related to the theme. As a result, this substantive cross-cutting issue will remain open until we determine, through our inspections, that corrective actions implemented in accordance with your improvement plan have resulted in sustained improved performance.


Also, our September 2, 2008, mid-cycle assessment letter identified a substantive cross-cutting issue in the area of problem identification and resolution associated with the corrective action program component. Three themes were identified within the corrective action program component for (1) a low enough threshold for identifying problems [P.1 (a)], (2) thoroughness of problem evaluation [P.1(c)], and (3) appropriateness of corrective actions [P.1 (d)] as the basis for the substantive cross-cutting issue. During this assessment, the substantive cross-cutting issue will remain open in all three areas.
Our mid-cycle assessment letter dated September 2, 2008, identified a substantive cross-cutting 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 cross-cutting issue at that time was five findings which composed a theme. During this assessment period, the number of findings increased to six findings related to the theme of failure to have complete, accurate, and up-to-date documentation, procedures, and/or work packages. These findings affected the Initiating Events, Mitigating Systems, and the Pubic Radiation Safety cornerstones.


First, at the 2008 mid-cycle assessment, a theme for an inadequate threshold for identifying problems was identified as part of a substantive cross-cutting issue in problem identification and resolution. At that time, there were five issues related to this theme. The theme had been identified at the 2007 annual assessment, but no substantive cross-cutting issue was identified because the issue had recently been identified to you and you had not had time to develop corrective action. In our 2008 mid-cycle assessment letter, we stated that this substantive cross-cutting issue would remain open until we determined that your corrective actions had
Examples include: an inadequate surveillance procedure that did not include all emergency core cooling vent valves, a procedure that did not include acceptance criteria for gaps in the containment sump, an inadequate procedure that resulted in the loss of all condensate pumps and a subsequent reactor trip, and an inadequate switchyard maintenance procedure that lead to a loss of all offsite power. During a public meeting with the NRC on October 21, 2008, you


been effective. During a public meeting with the NRC on October 21, 2008, you informed us that you had taken corrective action which had resulted in an increase in the number of items entered into you corrective action program. We noted this specific improvement by observing that during this assessment period, there was only one finding related to the theme of failure to have an adequate threshold for identifying problems. However, we also observed that there were over 30 NRC identified findings in this assessment period. Ev en though your staff is identifying more issues, your actions have not proven effective based on the large number of NRC identified findings during this assessment peri od. Therefore the substantive cross-cutting theme associated with a low enough threshold for identifying problems will remain open.
Wolf Creek Nuclear Operating Corp -2-informed us that you had recently completed a root cause analysis of your human performance issues. You also 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. The actions that you implemented have not yet proven effective in substantially mitigating this cross-cutting theme as evidenced by the number of existing findings related to the theme. As a result, this substantive cross-cutting issue will remain open until we determine, through our inspections, that corrective actions implemented in accordance with your improvement plan have resulted in sustained improved performance.


Next, at the 2008 mid-cycle assessment, a theme associated with the thoroughness of problem evaluation was also identified as part of a substantive cross-cutting issue in problem identification and resolution based on seven related findings. During this assessment period, there were eight findings related to the theme of failing to completely evaluate problems, all in the Mitigating Systems cornerstone. Examples include: failing to ensure submerged safety-related 4160 volt cables were qualified for service, improper evaluation of mechanical agitation of a check valve, improper use of a calculation to justify the operability of emergency core cooling systems containing voids, and failure to perform an adequate acceptance review of a vendor containment sump calculation. In our 2 008 mid-cycle assessment letter, we stated that this new substantive cross-cutting issue would remain open until we determined that your
Also, our September 2, 2008, mid-cycle assessment letter identified a substantive cross-cutting issue in the area of problem identification and resolution associated with the corrective action program component. Three themes were identified within the corrective action program component for (1) a low enough threshold for identifying problems [P.1 (a)], (2) thoroughness of problem evaluation [P.1(c)], and (3) appropriateness of corrective actions [P.1 (d)] as the basis for the substantive cross-cutting issue. During this assessment, the substantive cross-cutting issue will remain open in all three areas.


corrective actions had been effective.
First, at the 2008 mid-cycle assessment, a theme for an inadequate threshold for identifying problems was identified as part of a substantive cross-cutting issue in problem identification and resolution. At that time, there were five issues related to this theme. The theme had been identified at the 2007 annual assessment, but no substantive cross-cutting issue was identified because the issue had recently been identified to you and you had not had time to develop corrective action. In our 2008 mid-cycle assessment letter, we stated that this substantive cross-cutting issue would remain open until we determined that your corrective actions had been effective. During a public meeting with the NRC on October 21, 2008, you informed us that you had taken corrective action which had resulted in an increase in the number of items entered into you corrective action program. We noted this specific improvement by observing that during this assessment period, there was only one finding related to the theme of failure to have an adequate threshold for identifying problems. However, we also observed that there were over 30 NRC identified findings in this assessment period. Even though your staff is identifying more issues, your actions have not proven effective based on the large number of NRC identified findings during this assessment period. Therefore the substantive cross-cutting theme associated with a low enough threshold for identifying problems will remain open.


During a public meeting with the NRC on October 21, 2008, you informed us that you had completed a root cause analysis for noted deficiencies related to problem identification and resolution. You informed us that you had implemented a management review program of all condition reports and established an Engineering Standards Team as part of your corrective actions for this theme. We did not observe improvement during this annual assessment period, based on the continued high  
Next, at the 2008 mid-cycle assessment, a theme associated with the thoroughness of problem evaluation was also identified as part of a substantive cross-cutting issue in problem identification and resolution based on seven related findings. During this assessment period, there were eight findings related to the theme of failing to completely evaluate problems, all in the Mitigating Systems cornerstone. Examples include: failing to ensure submerged safety-related 4160 volt cables were qualified for service, improper evaluation of mechanical agitation of a check valve, improper use of a calculation to justify the operability of emergency core cooling systems containing voids, and failure to perform an adequate acceptance review of a vendor containment sump calculation. In our 2008 mid-cycle assessment letter, we stated that this new substantive cross-cutting issue would remain open until we determined that your corrective actions had been effective. During a public meeting with the NRC on October 21, 2008, you informed us that you had completed a root cause analysis for noted deficiencies related to problem identification and resolution. You informed us that you had implemented a management review program of all condition reports and established an Engineering Standards Team as part of your corrective actions for this theme. We did not observe improvement during this annual assessment period, based on the continued high


Wolf Creek Nuclear Operating Corp - 3 - number of findings related to the theme. Therefore, the substantive cross-cutting theme associated with the thoroughness of problem evaluation will remain open.
Wolf Creek Nuclear Operating Corp -3-number of findings related to the theme. Therefore, the substantive cross-cutting theme associated with the thoroughness of problem evaluation will remain open.


Finally, at the 2008 mid-cycle assessment, a theme associated with the appropriateness of corrective actions was also identified as part of a substantive cross-cutting issue in problem identification and resolution based on seven related findings. During this assessment period, there were eight findings related to the theme of failing to employ effective corrective actions which affected the Mitigating Systems and Barrier Integrity cornerstones. Examples include:
Finally, at the 2008 mid-cycle assessment, a theme associated with the appropriateness of corrective actions was also identified as part of a substantive cross-cutting issue in problem identification and resolution based on seven related findings. During this assessment period, there were eight findings related to the theme of failing to employ effective corrective actions which affected the Mitigating Systems and Barrier Integrity cornerstones. Examples include:
ineffective corrective actions for a previously identified inadequate joint which leaked during a water hammer event, ineffective actions for manual valve stem friction which allowed unplanned transfer of water from the spent fuel pool, corrective actions which did not address the missed performance of an operability evaluation for a safety-related system, and failure to take corrective actions which addressed a failure to follow procedures and take compensatory action during a loss of annunciator event. In our 2008 mid-cycle assessment letter, we stated that this new substantive cross-cutting issue would remain open until we determined that your corrective actions had been effective. During a public me eting with the NRC on October 21, 2008, you informed us that you had completed a root cause analysis for noted deficiencies related to problem identification and resolution. You informed us that you had conducted training for site leadership on their role in the corrective action process and planned additional training for root cause evaluators as part of your corrective actions for this theme. We did not observe improvement during this annual assessment period, based on the continued high number of findings related to the theme. Therefore, the substantive cross-cutting theme associated with the appropriateness of corrective actions will remain open.
ineffective corrective actions for a previously identified inadequate joint which leaked during a water hammer event, ineffective actions for manual valve stem friction which allowed unplanned transfer of water from the spent fuel pool, corrective actions which did not address the missed performance of an operability evaluation for a safety-related system, and failure to take corrective actions which addressed a failure to follow procedures and take compensatory action during a loss of annunciator event. In our 2008 mid-cycle assessment letter, we stated that this new substantive cross-cutting issue would remain open until we determined that your corrective actions had been effective. During a public meeting with the NRC on October 21, 2008, you informed us that you had completed a root cause analysis for noted deficiencies related to problem identification and resolution. You informed us that you had conducted training for site leadership on their role in the corrective action process and planned additional training for root cause evaluators as part of your corrective actions for this theme. We did not observe improvement during this annual assessment period, based on the continued high number of findings related to the theme. Therefore, the substantive cross-cutting theme associated with the appropriateness of corrective actions will remain open.


As a result, this substantive cross-cutting issue in problem identification and resolution will remain open until we determine, through our inspections, that corrective actions implemented in accordance with your improvement plan have resulted in sustained improved performance.
As a result, this substantive cross-cutting issue in problem identification and resolution will remain open until we determine, through our inspections, that corrective actions implemented in accordance with your improvement plan have resulted in sustained improved performance.
Line 64: Line 57:
The inspections in the last nine months of the inspection plan are tentative and may be revised at the mid-cycle review.
The inspections in the last nine 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
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).
 
Wolf Creek Nuclear Operating Corp - 4 - If circumstances arise which cause us to change this inspection plan, we will contact you to discuss the change as soon as possible. Please contact Vincent Gaddy of my staff 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
 
===Enclosure:===
Wolf Creek Inspection/Activity Plan
 
cc w/enclosure:
Tim Sipe, Chairman Coffey County Commissioner


110 South 6th Street Burlington, KS 66839
Wolf Creek Nuclear Operating Corp -4-If circumstances arise which cause us to change this inspection plan, we will contact you to discuss the change as soon as possible. Please contact Vincent Gaddy of my staff at 817-860-8141 with any questions you may have regarding this letter or the inspection plan.


Kimberly Robrahn Coffey County Commissioner  
Sincerely,
/RA/
Dwight D. Chamberlain, Director Division of Reactor Projects Docket: 50-482 License: NPF-42 Enclosure:
Wolf Creek Inspection/Activity Plan cc w/enclosure:
Tim Sipe, Chairman Coffey County Commissioner 110 South 6th Street Burlington, KS 66839 Kimberly Robrahn Coffey County Commissioner 110 South 6th Street Burlington, KS 66839 Larry Crotts Coffey County Commissioner 110 South 6th Street Burlington, KS 66839 Bob Saueressig Coffey County Commissioner 110 South 6th Street Burlington, KS 66839 Fred Rowley, Vice Chairman Coffey County Commissioner 110 South 6th Street Burlington, KS 66839 Russel Stukey,Coffey County Emergency Preparedness 110 South 6th Street Burlington, KS 66839


110 South 6th Street Burlington, KS 66839
Wolf Creek Nuclear Operating Corp -5-Randy Rogers, Sheriff Coffey County Sheriffs Dept.


Larry Crotts Coffey County Commissioner
110 South 6th Street Burlington, KS 66839 The Honorable Rick Raymer Mayor, City of Burlington City Hall P.O. Box 207 Burlington, KS 66839 The Honorable Bill Freemen Mayor, City of LeRoy 713 Main Street LeRoy, KS 66857 The Honorable Mark Petterson Mayor, City of New Strawn City Hall P.O. Box 922 New Strawn, KS 66839-0922 The Honorable Larry Kelley Mayor, City of Gridley P.O. Box 182 Gridley, KS 66852 The Honorable Craig Meader Mayor, City of Waverly P.O. Box 308 Waverly, KS 66871 The Honorable Ed Fisher Mayor, City of Lebo P.O. Box 14 Lebo, KS 66856-0014 Dave Beck Allen County Emergency Preparedness Coordinator Allen County Courthouse P.O. Box 433 Iola, KS 66749 Rick Frevbert Lyon County Emergency Preparedness Coordinator 425 Mechanic St.


110 South 6th Street Burlington, KS 66839 Bob Saueressig Coffey County Commissioner 110 South 6th Street Burlington, KS 66839
Emporia, KS 66801


Fred Rowley, Vice Chairman Coffey County Commissioner 110 South 6th Street Burlington, KS 66839  
Wolf Creek Nuclear Operating Corp -6-Gary Benjamin Anderson County Emergency Preparedness Coordinator 315 Orange Street Garnett, KS 66032 Sheila Dale Osage County Emergency Manager P. O. Box 281 Lyndon, Kansas 66451 Institute of Nuclear Power Operations (INPO)
Records Center 700 Galleria Parkway SE, Suite 100 Atlanta, GA 30339 Vice President Operations/Plant Manager Wolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington, KS 66839 Jay Silberg, Esq.


Russel Stukey,Coffey County Emergency Preparedness 110 South 6th Street Burlington, KS 66839  
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


Wolf Creek Nuclear Operating Corp - 5 - Randy Rogers, Sheriff Coffey County Sheriff's Dept.
Wolf Creek Nuclear Operating Corp -7-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, Radiological Emergency Preparedness Section FEMA, Region VII 9221 Ward Parkway Suite 300 Kansas City, MO 64114-3372


110 South 6th Street Burlington, KS 66839
Wolf Creek Nuclear Operating Corp -8-Electronic distribution by RIV:
 
The Honorable Rick Raymer Mayor, City of Burlington
 
City Hall P.O. Box 207 Burlington, KS 66839 The Honorable Bill Freemen Mayor, City of LeRoy
 
713 Main Street LeRoy, KS 66857
 
The Honorable Mark Petterson Mayor, City of New Strawn
 
City Hall P.O. Box 922 New Strawn, KS 66839-0922
 
The Honorable Larry Kelley Mayor, City of Gridley P.O. Box 182 Gridley, KS 66852
 
The Honorable Craig Meader Mayor, City of Waverly P.O. Box 308 Waverly, KS 66871
 
The Honorable Ed Fisher Mayor, City of Lebo P.O. Box 14 Lebo, KS 66856-0014 Dave Beck
 
Allen County Emergency Preparedness Coordinator
 
Allen County Courthouse P.O. Box 433 Iola, KS 66749
 
Rick Frevbert Lyon County Emergency Preparedness Coordinator 425 Mechanic St.
 
Emporia, KS 66801
 
Wolf Creek Nuclear Operating Corp - 6 -
Gary Benjamin
 
Anderson County Emergency Preparedness Coordinator 315 Orange Street Garnett, KS 66032
 
Sheila Dale Osage County Emergency Manager P. O. Box 281 Lyndon, Kansas 66451 Institute of Nuclear Power Operations (INPO)
 
Records Center 700 Galleria Parkway SE, Suite 100 Atlanta, GA 30339 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
 
Wolf Creek Nuclear Operating Corp - 7 -
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, Radiological Emergency Preparedness Section FEMA, Region VII 9221 Ward Parkway
 
Suite 300 Kansas City, MO 64114-3372
 
Wolf Creek Nuclear Operating Corp - 8 -
Electronic distribution by RIV:
Regional Administrator (Elmo.Collins@nrc.gov)
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)
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 Director (Roy.Caniano@nrc.gov)
DRP Deputy Director (Troy.Pruett@nrc.gov)
DRP Deputy Director (Troy.Pruett@nrc.gov)
Senior Resident Inspector (Chris.Long@nrc.gov)
Senior Resident Inspector (Chris.Long@nrc.gov)
Branch Chief, DRP/ (Vincent.Gaddy@nrc.gov) Senior Project Engineer, DRP/ (Richard.Deese@nrc.gov) Team Leader, DRP/TSS (Chuck.Paulk@nrc.gov) RITS Coordinator (Marisa.Herrera@nrc.gov) Public Affairs Officer (Victor.Dricks@nrc.gov)
Branch Chief, DRP/ (Vincent.Gaddy@nrc.gov)
Regional State Liaison Officer (Bill.Maier@nrc.gov) RA Secretary (Lucy.Owen@nrc.gov) DRA Secretary (Judy.Kilcrease@nrc.gov)
Senior Project Engineer, DRP/ (Richard.Deese@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/EB1 (Thomas.Farnholtz@nrc.gov)
Branch Chief, DRS/EB2 (Neil.OKeefe@nrc.gov)  
Branch Chief, DRS/EB2 (Neil.OKeefe@nrc.gov)
 
Branch Chief, DRS/PSB1 (Michael.Shannon@nrc.gov)
Branch Chief, DRS/PSB1 (Michael.Shannon@nrc.gov)
Branch Chief, DRS/PSB2 (Greg.Werner@nrc.gov) Branch Chief, DRS/OB (Bernard.Stapleton@nrc.gov)
Branch Chief, DRS/PSB2 (Greg.Werner@nrc.gov)
Branch Chief, DRS/OB (Bernard.Stapleton@nrc.gov)
OEDO RIV Coordinator, Primary (Shawn.Williams@nrc.gov)
OEDO RIV Coordinator, Primary (Shawn.Williams@nrc.gov)
OEDO RIV Coordinator, Backup (Eugene.Guthrie@nrc.gov)
OEDO RIV Coordinator, Backup (Eugene.Guthrie@nrc.gov)
OEDO, TRPS (Tamara.Bloomer@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)
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)
Chief, PLB IV, DORL, NRR (Thomas.Hiltz@nrc.gov)
NRR Project Manager (Balwant.Singal@nrc.gov)  
NRR Project Manager (Balwant.Singal@nrc.gov)
 
RidsNrrDirslpab Resource@nrc.gov ROPreports.Resource@nrc.gov mortensengk@INPO.org File located: R:\_REACTORS\EOC and Midcycle\EOC Assessment Letters\2008-dated 3-4-09 SUNSI Rev Compl. 7 Yes No ADAMS  7 Yes No Reviewer Initials VGG Publicly Avail 7 Yes No Sensitive Yes 7 No Sens. Type Initials VGG RIV:C:DRP/B D:DRS D:DRP VGaddy  RJCaniano DDChamberlain
RidsNrrDirslpab Resource@nrc.gov ROPreports.Resource@nrc.gov mortensengk@INPO.org  
/RA/  /RA/ /RA/
2/23/2009 2/23/2009 2/24/2009 OFFICIAL RECORD COPY  T-Telephone E-Email F-Fax


File located: R:\_REACTORS\EOC and Midcycle\EOC Assessment Letters\2008-dated 3-4-09 SUNSI Rev Compl. Yes No ADAMS Yes No Reviewer Initials VGG Publicly Avail Yes No Sensitive Yes No Sens. Type Initials VGGRIV:C:DRP/B D:DRS D:DRP VGaddy RJCaniano DDChamberlain
Page 1 of 1     Wolf Creek 02/23/2009 12:43:40   Inspection / Activity Plan Report 22 03/01/2009 - 06/30/2010 Unit Planned Dates       No. of Staff Number Start End Inspection Activity   Title on Site EP1 - EP EXERCISE INSPECTION     3 1 06/01/2009 06/05/2009 IP 7111401 Exercise Evaluation 1 06/01/2009 06/05/2009 IP 7111404 Emergency Action Level and Emergency Plan Changes 1 06/01/2009 06/05/2009 IP 71151  Performance Indicator Verification EB1-17T - 50.59 & MODS     2 1 07/20/2009 07/31/2009 IP 7111117T Evaluations of Changes, Tests, or Experiments and Permanent Plant Modifications EXAM - INITIAL EXAM     6 1 07/13/2009 07/17/2009 X02419 INITIAL EXAM-WC (8/2009)
/RA/ /RA/ /RA/ 2/23/2009 2/23/2009 2/24/2009 OFFICIAL RECORD COPY T-Telephone E-Email F-Fax Inspection / Activity Plan Page 1 of 1 02/23/2009 12:43:40 Report 22 03/01/2009
1 08/17/2009 08/21/2009 X02419 INITIAL EXAM-WC (8/2009)
-06/30/2010 Unit Number Planned Dates Start End Inspection Activity Title No. of Staff on Site Wolf Creek EP1-EP EXERCISE INSPECTION 3 1 IP Exercise Evaluation 7111401 06/01/2009 06/05/2009 1 IP Emergency Action Level and Emergency Plan Changes 7111404 06/01/2009 06/05/2009 1 IP Performance Indicator Verification 71151 06/01/2009 06/05/2009 EB1-17T-50.59 & MODS 2 1 IP Evaluations of Changes, Tests, or Experiments and Permanent Plant Modifications 7111117T 07/20/2009 07/31/2009 EXAM-INITIAL EXAM 6 1 INITIAL EXAM-WC (8/2009)
EB1-08 - INSERVICE INSPECTION     2 1 10/10/2009 11/06/2009 IP 2515/172 Reactor Coolant System Dissimiliar Metal Butt Welds 1 10/10/2009 11/06/2009 IP 7111108P Inservice Inspection Activities - PWR RP-ORS3 - OCCUPATIONAL RADIATION SAFETY - ALARA     1 1 10/19/2009 10/23/2009 IP 7112101 Access Control to Radiologically Significant Areas 1 10/19/2009 10/23/2009 IP 7112102 ALARA Planning and Controls 1 10/19/2009 10/23/2009 IP 71151  Performance Indicator Verification RP-ORS4 - OCCUPATIONAL RADIATION SAFETY - ACCESS   1 1 10/26/2009 10/30/2009 IP 7112101 Access Control to Radiologically Significant Areas 1 10/26/2009 10/30/2009 IP 7112102 ALARA Planning and Controls 1 10/26/2009 10/30/2009 IP 71151  Performance Indicator Verification EP-1 - BIENNIAL EP PROGRAM INSPECTION     1 1 06/21/2010 06/25/2010 IP 7111402 Alert and Notification System Testing 1 06/21/2010 06/25/2010 IP 7111403 Emergency Response Organization Augmentation Testing 1 06/21/2010 06/25/2010 IP 7111404 Emergency Action Level and Emergency Plan Changes 1 06/21/2010 06/25/2010 IP 7111405 Correction of Emergency Preparedness Weaknesses and Deficiencies 1 06/21/2010 06/25/2010 IP 71151-EP01 Drill/Exercise Performance 1 06/21/2010 06/25/2010 IP 71151-EP02 ERO Drill Participation 1 06/21/2010 06/25/2010 IP 71151-EP03 Alert & Notification System This report does not include INPO and OUTAGE activities.
X02419 07/13/2009 07/17/2009 1 INITIAL EXAM-WC (8/2009)
X02419 08/17/2009 08/21/2009 EB1-08-INSERVICE INSPECTION 2 1 IP Reactor Coolant System Dissimiliar Metal Butt Welds 2515/172 10/10/2009 11/06/2009 1 IP Inservice Inspection Activities - PWR 7111108P 10/10/2009 11/06/2009 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 10/26/2009 10/30/2009 1 IP A LARA Planning and Controls 7112102 10/26/2009 10/30/2009 1 IP Performance Indicator Verification 71151 10/26/2009 10/30/2009 EP-1-BIENNIAL EP PROGRAM INSPECTION 1 1 IP A lert and Notification System Testing 7111402 06/21/2010 06/25/2010 1 IP Emergency Response Organization Augmentation Testing 7111403 06/21/2010 06/25/2010 1 IP Emergency Action Level and Emergency Plan Changes 7111404 06/21/2010 06/25/2010 1 IP Correction of Emergency Preparedness Weaknesses and Deficiencies 7111405 06/21/2010 06/25/2010 1 IP Drill/Exercise Performance 71151-EP01 06/21/2010 06/25/2010 1 IP ERO Drill Participation 71151-EP02 06/21/2010 06/25/2010 1 IP A lert & Notification System 71151-EP03 06/21/2010 06/25/2010 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.
}}
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Latest revision as of 08:29, 14 November 2019

Annual Assessment Letter and Inspection Plan 2008 (NRC Inspection Report 05000482-09-001)
ML090630773
Person / Time
Site: Wolf Creek Wolf Creek Nuclear Operating Corporation icon.png
Issue date: 03/04/2009
From: Chamberlain D
NRC/RGN-IV/DRP
To: Muench R
Wolf Creek
References
IR-09-001
Download: ML090630773 (9)
v • d • e


Text

UNITED STATES NU C LE AR RE G ULATO RY C O M M I S S I O N rch 4, 2009

SUBJECT:

ANNUAL ASSESSMENT LETTER - WOLF CREEK GENERATING STATION (NRC INSPECTION REPORT 05000482/2009001)

Dear Mr. Muench:

On February 11, 2009, the NRC staff completed its performance review of the Wolf Creek Generating Station. Our technical staff reviewed performance indicators for the most recent quarter and inspection results for the period from January 1 through December 31, 2008. 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-Related Information" will include the security cornerstone review and resultant inspection plan.

Overall, the Wolf Creek Generating Station operated in a manner that preserved public health and safety and fully met all cornerstone objectives. Plant performance for the most recent quarter, as well as for the first three quarters of the assessment cycle, 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). Therefore, we plan to conduct reactor oversight process baseline inspections at your facility.

Our mid-cycle assessment letter dated September 2, 2008, identified a substantive cross-cutting 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 cross-cutting issue at that time was five findings which composed a theme. During this assessment period, the number of findings increased to six findings related to the theme of failure to have complete, accurate, and up-to-date documentation, procedures, and/or work packages. These findings affected the Initiating Events, Mitigating Systems, and the Pubic Radiation Safety cornerstones.

Examples include: an inadequate surveillance procedure that did not include all emergency core cooling vent valves, a procedure that did not include acceptance criteria for gaps in the containment sump, an inadequate procedure that resulted in the loss of all condensate pumps and a subsequent reactor trip, and an inadequate switchyard maintenance procedure that lead to a loss of all offsite power. During a public meeting with the NRC on October 21, 2008, you

Wolf Creek Nuclear Operating Corp -2-informed us that you had recently completed a root cause analysis of your human performance issues. You also 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. The actions that you implemented have not yet proven effective in substantially mitigating this cross-cutting theme as evidenced by the number of existing findings related to the theme. As a result, this substantive cross-cutting issue will remain open until we determine, through our inspections, that corrective actions implemented in accordance with your improvement plan have resulted in sustained improved performance.

Also, our September 2, 2008, mid-cycle assessment letter identified a substantive cross-cutting issue in the area of problem identification and resolution associated with the corrective action program component. Three themes were identified within the corrective action program component for (1) a low enough threshold for identifying problems [P.1 (a)], (2) thoroughness of problem evaluation P.1(c), and (3) appropriateness of corrective actions [P.1 (d)] as the basis for the substantive cross-cutting issue. During this assessment, the substantive cross-cutting issue will remain open in all three areas.

First, at the 2008 mid-cycle assessment, a theme for an inadequate threshold for identifying problems was identified as part of a substantive cross-cutting issue in problem identification and resolution. At that time, there were five issues related to this theme. The theme had been identified at the 2007 annual assessment, but no substantive cross-cutting issue was identified because the issue had recently been identified to you and you had not had time to develop corrective action. In our 2008 mid-cycle assessment letter, we stated that this substantive cross-cutting issue would remain open until we determined that your corrective actions had been effective. During a public meeting with the NRC on October 21, 2008, you informed us that you had taken corrective action which had resulted in an increase in the number of items entered into you corrective action program. We noted this specific improvement by observing that during this assessment period, there was only one finding related to the theme of failure to have an adequate threshold for identifying problems. However, we also observed that there were over 30 NRC identified findings in this assessment period. Even though your staff is identifying more issues, your actions have not proven effective based on the large number of NRC identified findings during this assessment period. Therefore the substantive cross-cutting theme associated with a low enough threshold for identifying problems will remain open.

Next, at the 2008 mid-cycle assessment, a theme associated with the thoroughness of problem evaluation was also identified as part of a substantive cross-cutting issue in problem identification and resolution based on seven related findings. During this assessment period, there were eight findings related to the theme of failing to completely evaluate problems, all in the Mitigating Systems cornerstone. Examples include: failing to ensure submerged safety-related 4160 volt cables were qualified for service, improper evaluation of mechanical agitation of a check valve, improper use of a calculation to justify the operability of emergency core cooling systems containing voids, and failure to perform an adequate acceptance review of a vendor containment sump calculation. In our 2008 mid-cycle assessment letter, we stated that this new substantive cross-cutting issue would remain open until we determined that your corrective actions had been effective. During a public meeting with the NRC on October 21, 2008, you informed us that you had completed a root cause analysis for noted deficiencies related to problem identification and resolution. You informed us that you had implemented a management review program of all condition reports and established an Engineering Standards Team as part of your corrective actions for this theme. We did not observe improvement during this annual assessment period, based on the continued high

Wolf Creek Nuclear Operating Corp -3-number of findings related to the theme. Therefore, the substantive cross-cutting theme associated with the thoroughness of problem evaluation will remain open.

Finally, at the 2008 mid-cycle assessment, a theme associated with the appropriateness of corrective actions was also identified as part of a substantive cross-cutting issue in problem identification and resolution based on seven related findings. During this assessment period, there were eight findings related to the theme of failing to employ effective corrective actions which affected the Mitigating Systems and Barrier Integrity cornerstones. Examples include:

ineffective corrective actions for a previously identified inadequate joint which leaked during a water hammer event, ineffective actions for manual valve stem friction which allowed unplanned transfer of water from the spent fuel pool, corrective actions which did not address the missed performance of an operability evaluation for a safety-related system, and failure to take corrective actions which addressed a failure to follow procedures and take compensatory action during a loss of annunciator event. In our 2008 mid-cycle assessment letter, we stated that this new substantive cross-cutting issue would remain open until we determined that your corrective actions had been effective. During a public meeting with the NRC on October 21, 2008, you informed us that you had completed a root cause analysis for noted deficiencies related to problem identification and resolution. You informed us that you had conducted training for site leadership on their role in the corrective action process and planned additional training for root cause evaluators as part of your corrective actions for this theme. We did not observe improvement during this annual assessment period, based on the continued high number of findings related to the theme. Therefore, the substantive cross-cutting theme associated with the appropriateness of corrective actions will remain open.

As a result, this substantive cross-cutting issue in problem identification and resolution will remain open until we determine, through our inspections, that corrective actions implemented in accordance with your improvement plan have resulted in sustained improved performance.

Since this is the second consecutive assessment letter identifying the same cross-cutting issues in problem identification and resolution and human performance, we request that you provide a response to these issues at the annual public meeting. We also ask that you provide a written response to these issues and also schedule a separate public meeting to discuss these issues.

Your response should provide details on your corrective actions planned to address the cross-cutting theme including schedule, milestones, and performance monitoring metrics.

The enclosed inspection plan details the inspections, less those related to physical protection scheduled through June 30, 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 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).

Wolf Creek Nuclear Operating Corp -4-If circumstances arise which cause us to change this inspection plan, we will contact you to discuss the change as soon as possible. Please contact Vincent Gaddy of my staff 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 Enclosure:

Wolf Creek Inspection/Activity Plan cc w/enclosure:

Tim Sipe, Chairman Coffey County Commissioner 110 South 6th Street Burlington, KS 66839 Kimberly Robrahn Coffey County Commissioner 110 South 6th Street Burlington, KS 66839 Larry Crotts Coffey County Commissioner 110 South 6th Street Burlington, KS 66839 Bob Saueressig Coffey County Commissioner 110 South 6th Street Burlington, KS 66839 Fred Rowley, Vice Chairman Coffey County Commissioner 110 South 6th Street Burlington, KS 66839 Russel Stukey,Coffey County Emergency Preparedness 110 South 6th Street Burlington, KS 66839

Wolf Creek Nuclear Operating Corp -5-Randy Rogers, Sheriff Coffey County Sheriffs Dept.

110 South 6th Street Burlington, KS 66839 The Honorable Rick Raymer Mayor, City of Burlington City Hall P.O. Box 207 Burlington, KS 66839 The Honorable Bill Freemen Mayor, City of LeRoy 713 Main Street LeRoy, KS 66857 The Honorable Mark Petterson Mayor, City of New Strawn City Hall P.O. Box 922 New Strawn, KS 66839-0922 The Honorable Larry Kelley Mayor, City of Gridley P.O. Box 182 Gridley, KS 66852 The Honorable Craig Meader Mayor, City of Waverly P.O. Box 308 Waverly, KS 66871 The Honorable Ed Fisher Mayor, City of Lebo P.O. Box 14 Lebo, KS 66856-0014 Dave Beck Allen County Emergency Preparedness Coordinator Allen County Courthouse P.O. Box 433 Iola, KS 66749 Rick Frevbert Lyon County Emergency Preparedness Coordinator 425 Mechanic St.

Emporia, KS 66801

Wolf Creek Nuclear Operating Corp -6-Gary Benjamin Anderson County Emergency Preparedness Coordinator 315 Orange Street Garnett, KS 66032 Sheila Dale Osage County Emergency Manager P. O. Box 281 Lyndon, Kansas 66451 Institute of Nuclear Power Operations (INPO)

Records Center 700 Galleria Parkway SE, Suite 100 Atlanta, GA 30339 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

Wolf Creek Nuclear Operating Corp -7-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, Radiological Emergency Preparedness Section FEMA, Region VII 9221 Ward Parkway Suite 300 Kansas City, MO 64114-3372

Wolf Creek Nuclear Operating Corp -8-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)

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

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

Senior Project Engineer, DRP/ (Richard.Deese@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 (Bernard.Stapleton@nrc.gov)

OEDO RIV Coordinator, Primary (Shawn.Williams@nrc.gov)

OEDO RIV Coordinator, Backup (Eugene.Guthrie@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 ROPreports.Resource@nrc.gov mortensengk@INPO.org File located: R:\_REACTORS\EOC and Midcycle\EOC Assessment Letters\2008-dated 3-4-09 SUNSI Rev Compl. 7 Yes No ADAMS 7 Yes No Reviewer Initials VGG Publicly Avail 7 Yes No Sensitive Yes 7 No Sens. Type Initials VGG RIV:C:DRP/B D:DRS D:DRP VGaddy RJCaniano DDChamberlain

/RA/ /RA/ /RA/

2/23/2009 2/23/2009 2/24/2009 OFFICIAL RECORD COPY T-Telephone E-Email F-Fax

Page 1 of 1 Wolf Creek 02/23/2009 12:43:40 Inspection / Activity Plan Report 22 03/01/2009 - 06/30/2010 Unit Planned Dates No. of Staff Number Start End Inspection Activity Title on Site EP1 - EP EXERCISE INSPECTION 3 1 06/01/2009 06/05/2009 IP 7111401 Exercise Evaluation 1 06/01/2009 06/05/2009 IP 7111404 Emergency Action Level and Emergency Plan Changes 1 06/01/2009 06/05/2009 IP 71151 Performance Indicator Verification EB1-17T - 50.59 & MODS 2 1 07/20/2009 07/31/2009 IP 7111117T Evaluations of Changes, Tests, or Experiments and Permanent Plant Modifications EXAM - INITIAL EXAM 6 1 07/13/2009 07/17/2009 X02419 INITIAL EXAM-WC (8/2009)

1 08/17/2009 08/21/2009 X02419 INITIAL EXAM-WC (8/2009)

EB1-08 - INSERVICE INSPECTION 2 1 10/10/2009 11/06/2009 IP 2515/172 Reactor Coolant System Dissimiliar Metal Butt Welds 1 10/10/2009 11/06/2009 IP 7111108P Inservice Inspection Activities - PWR RP-ORS3 - OCCUPATIONAL RADIATION SAFETY - ALARA 1 1 10/19/2009 10/23/2009 IP 7112101 Access Control to Radiologically Significant Areas 1 10/19/2009 10/23/2009 IP 7112102 ALARA Planning and Controls 1 10/19/2009 10/23/2009 IP 71151 Performance Indicator Verification RP-ORS4 - OCCUPATIONAL RADIATION SAFETY - ACCESS 1 1 10/26/2009 10/30/2009 IP 7112101 Access Control to Radiologically Significant Areas 1 10/26/2009 10/30/2009 IP 7112102 ALARA Planning and Controls 1 10/26/2009 10/30/2009 IP 71151 Performance Indicator Verification EP-1 - BIENNIAL EP PROGRAM INSPECTION 1 1 06/21/2010 06/25/2010 IP 7111402 Alert and Notification System Testing 1 06/21/2010 06/25/2010 IP 7111403 Emergency Response Organization Augmentation Testing 1 06/21/2010 06/25/2010 IP 7111404 Emergency Action Level and Emergency Plan Changes 1 06/21/2010 06/25/2010 IP 7111405 Correction of Emergency Preparedness Weaknesses and Deficiencies 1 06/21/2010 06/25/2010 IP 71151-EP01 Drill/Exercise Performance 1 06/21/2010 06/25/2010 IP 71151-EP02 ERO Drill Participation 1 06/21/2010 06/25/2010 IP 71151-EP03 Alert & Notification System This report does not include INPO and OUTAGE activities.

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

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