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{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION REGION IV 1600 E LAMAR BLVD ARLINGTON, TX 76011
[[Issue date::September 1, 2015]]
-4511 September 1, 2015 Louis P. Cortopassi, Site Vice President Omaha Public Power District Fort Calhoun Station P.O. Box 550 Fort Calhoun, NE 68023
-0550 Subject: MID-CYCLE ASSESSMENT LETTER FOR FORT CALHOUN STATION (REPORT 05000285/201500 5)


Louis P. Cortopassi, Site Vice President Omaha Public Power District Fort Calhoun Station P.O. Box 550 Fort Calhoun, NE 68023-0550 Subject: MID-CYCLE ASSESSMENT LETTER FOR FORT CALHOUN STATION (REPORT 05000285/2015005)
==Dear Mr. Cortopassi:==
On August 13
, 2015, the Nuclear Regulatory Commission (
NRC) completed its mid
-cycle performance review of the Fort Calhoun Station
. The NRC reviewed the most
-recent quarterly performance indicators (PIs)
, inspection results
, and enforcement actions from July 1, 2014, through June 30, 2015. This letter informs you of the NRC's assessment of your facility during this period and its plans for future inspections at your facility. The NRC determined that overall, the Fort Calhoun Station operated in a manner that preserved public health and safety and met all cornerstone objectives.
 
The NRC determined the performance at Fort Calhoun Station during the most recent quarter was within the Licensee Response Column of the NRC
's Reactor Oversight Process (ROP) Action Matrix because all inspection findings had very low (i.e., Green) safety significance, and all PIs indicated that your performance was within the nominal, expected range (i.e., Green). Therefore, the NRC plans to conduct ROP baseline inspections at your facility.
 
By letter dated March 30, 2015, (ADAMS Accession No. ML15089A085), the NRC informed you of the transition of regulatory oversight of Fort Calhoun Station from the Inspection Manual Chapter 0350 "Oversight of Operating Reactor Facilities in an Extended Shutdown as a Result of Significant Performance Problems," process to the Inspection Manual Chapter 0305, "Operating Reactor Assessment Program," oversight process. This transition became effective on April 1, 2015. Based on plant performance at the time, Fort Calhoun Station was placed in the Licensee Response Column of the ROP Action Matrix.


==Dear Mr. Cortopassi:==
During this mid-cycle performance review, the NRC identified a cross
On August 13, 2015, the Nuclear Regulatory Commission (NRC) completed its mid-cycle performance review of the Fort Calhoun Station. The NRC reviewed the most-recent quarterly performance indicators (PIs), inspection results, and enforcement actions from July 1, 2014, through June 30, 2015. This letter informs you of the NRC's assessment of your facility during this period and its plans for future inspections at your facility. The NRC determined that overall, the Fort Calhoun Station operated in a manner that preserved public health and safety and met all cornerstone objectives. The NRC determined the performance at Fort Calhoun Station during the most recent quarter was within the Licensee Response Column of the NRC's Reactor Oversight Process (ROP) Action Matrix because all inspection findings had very low (i.e., Green) safety significance, and all PIs indicated that your performance was within the nominal, expected range (i.e., Green). Therefore, the NRC plans to conduct ROP baseline inspections at your facility. By letter dated March 30, 2015, (ADAMS Accession No. ML15089A085), the NRC informed you of the transition of regulatory oversight of Fort Calhoun Station from the Inspection Manual Chapter 0350 "Oversight of Operating Reactor Facilities in an Extended Shutdown as a Result of Significant Performance Problems," process to the Inspection Manual Chapter 0305, "Operating Reactor Assessment Program," oversight process. This transition became effective on April 1, 2015. Based on plant performance at the time, Fort Calhoun Station was placed in the Licensee Response Column of the ROP Action Matrix. During this mid-cycle performance review, the NRC identified a cross-cutting theme in Human Performance involving Conservative Bias (H.14), with seven findings with this cross-cutting aspect identified over the twelve-month assessment period. The NRC also identified a cross-cutting theme in Problem Identification and Resolution associated with Evaluation (P.2), which also consisted of seven findings with this cross-cutting aspect identified over the twelve-month assessment period. In addition, the NRC identified overall cross-cutting themes in both the Human Performance and Problem Identification and Resolution areas, with 32 and 12 findings, respectively, with cross-cutting aspects in these areas. After consultation between Region IV and the Division of Regional Inspection Support in the Office of Nuclear Reactor Regulation, the NRC determined that this is the first assessment letter to identify these cross-cutting themes at Fort Calhoun Station. Therefore, the NRC has only documented the themes in this letter. If these themes continue through the next assessment period, the NRC will evaluate the effectiveness of your actions to address them to determine whether additional NRC follow-up should be accomplished, as described in Section 14.02 of Inspection Manual Chapter 0305, "Operating Reactor Assessment Program." From July 1, 2014, to June 30, 2015, the NRC issued six Severity Level IV traditional enforcement violations associated with impeding the regulatory process, four of which involved the implementation of the 10 CFR 50.59 process. Therefore, the NRC plans to conduct Inspection Procedure 92723, "Follow-Up Inspection for Three or More Severity Level IV Traditional Enforcement Violations in the Same Area in a 12-Month Period," to follow-up on these violations. The enclosed inspection plan lists the inspections scheduled through June 30, 2017. Routine inspections performed by resident inspectors are not included in the inspection plan. The inspections listed during the second half of the inspection plan are tentative and may be revised at the end-of-cycle performance review. The NRC provides the inspection plan to allow for the resolution of any scheduling conflicts and personnel availability issues. If circumstances warrant any changes to the inspection plan, the NRC will discuss those changes with you as soon as possible. This inspection plan does not include security related inspections, which will be sent via separate, non-publicly available correspondence. In addition, to monitor your continuing efforts to sustain improved plant performance and comply with the commitments identified in our December 17, 2013 Confirmatory Action Letter EA-13-243 (ADAMS ML13351A395), NRC inspections will be conducted for the remaining open items in coordination with their completion. In response to the accident at Fukushima, the Commission issued Order EA-12-049, "Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events," which requires licensees to develop, implement, and maintain guidance and strategies to maintain or restore core cooling, containment, and spent fuel pool cooling capabilities following a beyond-design-basis external event. Additionally, the Commission issued Order EA-12-051, "Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation," which requires licensees to have a reliable means of remotely monitoring wide-range Spent Fuel Pool levels to support effective prioritization of event mitigation and recovery actions in the event of a beyond-design-basis external event. The NRC is conducting audits of licensee efforts towards compliance with these Orders. This audit includes an onsite component in order for the NRC to evaluate licensee plans for complying with the Orders, as described in site-specific submittals, and to receive and review information relative to associated open items. This onsite activity will occur in the months prior to a declaration of compliance for the site, and will aid staff in development of a Final Safety Evaluation for the site. The date for the onsite component at your site is being coordinated with your staff. To allow sufficient time for preparations, a site-specific audit plan for the visit will be provided in advance. In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390 of the NRC's "Rules of Practice," a copy of this letter will be 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). Please contact me at 817-200-1173 with any questions you have regarding this letter.
-cutting theme in Human Performance involving Conservative Bias (H.14), with seven findings with this cross
-cutting aspect identified over the twelve
-month assessment period. The NRC also identified a cross
-cutting theme in Problem Identification and Resolution associated with Evaluation (P.2),
which also consisted of seven findings with this cross
-cutting aspect identified over the twelve
-month assessment period.
 
In addition, the NRC identified overall cross
-cutting themes in both the Human Performance and Problem Identification and Resolution areas, with 32 and 12 findings
, respectively
, with cross
-cutting aspects in these areas.
 
After consultation between Region IV and the Division of Regional Inspection Support in the Office of Nuclear Reactor Regulation, the NRC determined that this is the first assessment letter to identify these cross
-cutting themes at Fort Calhoun Station. Therefore, the NRC has only documented the themes in this letter. If these themes continue through the next assessment period, the NRC will evaluate the effectiveness of your actions to address the m to determine whether additional NRC follow
-up should be accomplished, as described in Section 14.02 of Inspection Manual Chapter 0305, "Operating Reactor Assessment Program."
 
From July 1, 2014, to June 30, 2015, the NRC issued six Severity Level IV traditional enforcement violations associated with impeding the regulatory process, four of which involved the implementation of the 10 CFR 50.59 process. Therefore, the NRC plans to conduct Inspection Procedure 92723, "Follow
-Up Inspection for Three or More Severity Level IV Traditional Enforcement Violations in the Same Area in a 12
-Month Period," to follow
-up on these violations
. The enclosed inspection plan lists the inspections scheduled through June 30, 2017. Routine inspections performed by resident inspectors are not included in the inspection plan. The inspections listed during the second half of the inspection plan are tentative and may be revised at the end
-of-cycle performance review. The NRC provides the inspection plan to allow for the resolution of any scheduling conflicts and personnel availability issues. If circumstances warrant any changes to the inspection plan, the NRC will discuss those changes with you as soon as possible. This inspection plan does not include security related inspections, which will be sent via separate, non
-publicly available correspondence.
 
In addition, to monitor your continuing efforts to sustain improved plant performance and comply with the commitments identified in our December 17, 2013 Confirmatory Action Letter EA
-13-243 (ADAMS ML13351A395)
, NRC inspections will be conducted for the remaining open items in coordination with their completion.
 
In response to the accident at Fukushima, the Commission issued Order EA
-12-049, "Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond
-Design-Basis External Events," which requires licensees to develop, implement, and maintain guidance and strategies to maintain or restore core cooling, containment, and spent fuel pool cooling capabilities following a beyond
-design-basis external event. Additionally, the Commission issued Order EA
-12-051, "Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation," which requires licensees to have a reliable means of remotely monitoring wide-range Spent Fuel Pool levels to support effective prioritization of event mitigation and recovery actions in the event of a beyond
-design-basis external event. The NRC is conducting audits of licensee efforts towards compliance with these Orders. This audit includes an onsite component in order for the NRC to evaluate licensee plans for complying with the Orders, as described in site
-specific submittals, and to receive and review information relative to associated open items.
 
This onsite activity will occur in the months prior to a declaration of compliance for the site, and will aid staff in development of a Final Safety Evaluation for the site.
 
The date for the onsite component at your site is being coordinated with your staff.
 
To allow sufficient time for preparations
, a site-specific audit plan for the visit will be provided in advance
. In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390 of the NRC
's "Rules of Practice,
" a copy of this letter will be 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
). Please contact me at 817-200-1173 with any questions you have regarding this letter.


Sincerely,/RA/ Geoffrey B. Miller Chief, Project Branch D Division of Reactor Projects Docket: 50-285 License: DPR-40  
Sincerely,/RA/ Geoffrey B. Miller Chief, Project Branch D Division of Reactor Projects Docket: 50
-285 License: DPR
-40  


===Enclosure:===
===Enclosure:===
Fort Calhoun Station Inspection/Activity Plan In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390 of the NRC's "Rules of Practice," a copy of this letter will be 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). Please contact me at 817-200-1173 with any questions you have regarding this letter.
Fort Calhoun Station Inspection/Activity Plan In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390 of the NRC's "Rules of Practice," a copy of this letter will be 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
). Please contact me at 817-200-1173 with any questions you have regarding this letter.


Sincerely,/RA/ Geoffrey B. Miller Chief, Project Branch D Division of Reactor Projects Docket: 50-285 License: DPR-40  
Sincerely,/RA/ Geoffrey B. Miller Chief, Project Branch D Division of Reactor Projects Docket: 50
-285 License: DPR
-40  


===Enclosure:===
===Enclosure:===
Fort Calhoun Station Inspection/Activity Plan DISTRIBUTION: See next page ADAMS Accession No. SUNSI Review By: GBM ADAMS Yes No Non-Sensitive Sensitive Publicly Available Non-Publicly Available OFFICE C:DRP/D D:DRS D:DRP NAME GMiller AVegel TPruett SIGNATURE /RA/ /RA/ /RA/ DATE 8/27/15 8/27/15 8/27/15 Letter to Louis from Geoffrey B. Miller dated September 1, 2015 Subject: MID-CYCLE ASSESSMENT LETTER FOR FORT CALHOUN STATION (REPORT 05000285/2015005)
Fort Calhoun Station Inspection/Activity Plan DISTRIBUTION: See next page ADAMS Accession No. SUNSI Review By: GBM ADAMS Yes No Non-Sensitive Sensitive Publicly Available Non-Publicly Available OFFICE C:DRP/D D:DRS D:DRP NAME GMiller AVegel TPruett SIGNATURE
DISTRIBUTION: Regional Administrator (Marc.Dapas@nrc.gov) Deputy Regional Administrator (Kriss.Kennedy@nrc.gov) DRP Director (Troy.Pruett@nrc.gov) DRP Deputy Director (Ryan.Lantz@nrc.gov) DRS Director (Anton.Vegel@nrc.gov) DRS Deputy Director (Jeff.Clark@nrc.gov) RIV Branch Chief, DRP/D (Geoffrey.Miller@nrc.gov) Senior Resident Inspector (Max.Schneider@nrc.gov) Resident Inspector (Brian.Cummings@nrc.gov) Senior Project Engineer, DRP/D (Bob.Hagar@nrc.gov) FCS Administrative Assistant (Janise.Schwee@nrc.gov) RIV Public Affairs Officer (Victor.Dricks@nrc.gov) RIV Public Affairs Officer (Lara.Uselding@nrc.gov) RIV State Liaison Officer (Bill.Maier@nrc.gov) Project Manager (Fred.Lyon@nrc.gov) Acting Team Lead, DRS/TSS (Eric.Ruesch@nrc.gov) Director, DIRS, NRR (Scott.Morris@nrc.gov) Deputy Director, DIRS, NRR (Allen.Howe@nrc.gov) Director, DORL, NRR (Anne.Boland@nrc.gov) Deputy Director, DORL, NRR (George.Wilson@nrc.gov) Director, NSIR/DPR (Rob.Lewis@nrc.gov) Chief, LPLIV-1, DORL, NRR (Michael.Markley@nrc.gov) Regional Counsel (Karla.Fuller@nrc.gov) RITS Coordinator (Marisa.Herrera@nrc.gov) Technical Support Assistant (Loretta.Williams@nrc.gov) Congressional Affairs Officer (Jenny.Weil@nrc.gov) RIV Congressional Affairs Officer (Angel.Moreno@nrc.gov) RIV/ETA: OEDO (Cindy.Rosales-Cooper@nrc.gov) ROPassessment Resource@nrc.gov ROPreports@nrc.gov OEMail Resource@nrc.gov Electronic Distribution for Fort Calhoun Station Page 1 of 208/26/201514:07:16Report 22UnitNumberPlanned DatesStart EndInspection ActivityTitleNo. of Staffon SiteFort CalhounInspection / Activity Plan07/01/2015-06/30/2017EXAM-INITIAL OPERATOR EXAM41 INITIAL EXAM FC(02/2015)X0254411/16/201511/20/20151 INITIAL EXAM FC(02/2015)X0254412/14/201512/18/2015FCSSIT06-SPECIAL INSPECTION FOR AFW VALVES21 IPFollowup of Events and Notices of Enforcement Discretion7115306/29/201509/01/2015EP-2-HAB EXERCISE INSPECTION51 IPEmergency Action Level and Emergency Plan Changes711140408/03/201508/07/20151 IPExercise Evaluation - Hostile Action (HA) Event711140708/03/201508/07/2015EP-3-EP PERFORMANCE INDICATORS21 IPDrill/Exercise Performance71151-EP0108/03/201508/07/20151 IPERO Readiness71151-EP0208/03/201508/07/20151 IPAlert & Notification System Reliability71151-EP0308/03/201508/07/2015ISFSI-ROUTINE INSPECTION (1 WEEK IN THE MONTH)11 IPOperation Of An ISFSI6085509/01/201509/30/2015EB2-05T-TRIENNIAL FIRE PROTECTION INSPECTION51 IPFire Protection - NFPA 805 (Triennial)7111105X10/19/201510/23/20151 IPFire Protection - NFPA 805 (Triennial)7111105X11/02/201511/06/2015RS 24-RADIATION SAFETY21 IPOccupational ALARA Planning and Controls71124.0211/16/201511/20/20151 IPOccupational Dose Assessment71124.0411/16/201511/20/2015TSB 52B-BIENNIAL PI&R INSPECTION41 IPProblem Identification and Resolution71152B11/16/201511/20/20151 IPProblem Identification and Resolution71152B12/07/201512/11/2015INSP-BIENNIAL REQUAL INSPECTION21 IPLicensed Operator Requalification Program7111111B06/27/201607/01/2016RS 5678-RADIATION SAFETY - TEAM41 IPRadiation Monitoring Instrumentation71124.0507/18/201607/22/20161 IPRadioactive Gaseous and Liquid Effluent Treatment71124.0607/18/201607/22/20161 IPRadiological Environmental Monitoring Program71124.0707/18/201607/22/20161 IPRadioactive Solid Waste Processing and Radioactive Material Handling, Storage, and Transportation71124.0807/18/201607/22/2016EB1-17T-FCS PERM PLANT MODS & 50.59 INSPECTION31 IPEvaluations of Changes, Tests, and Experiments and Permanent Plant Modifications7111117T07/25/201608/12/2016This report does not include INPO and OUTAGE activities. This report shows only on-site and announced inspection procedures.
/RA/ /RA/ /RA/ DATE 8/27/15 8/27/15 8/27/15 Letter to Louis from Geoffrey B. Miller dated September 1, 2015 Subject: MID-CYCLE ASSESSMENT LETTER FOR FORT CALHOUN STATION (REPORT 05000285/201500 5)
DISTRIBUTION
: Regional Administrator (Marc.Dapas@nrc.gov)
Deputy Regional Administrator (Kriss.Kennedy@nrc.gov) DRP Director (Troy.Pruett@nrc.gov)
DRP Deputy Director (Ryan.Lantz@nrc.gov)
DRS Director (Anton.Vegel@nrc.gov)
DRS Deputy Director (Jeff.Clark@nrc.gov)
RIV Branch Chief, DRP/D (Geoffrey.Miller@nrc.gov)
Senior Resident Inspector (Max.Schneider@nrc.gov)
Resident Inspector (Brian.Cummings@nrc.gov)
Senior Project Engineer, DRP/
D (Bob.Hagar@nrc.gov)
FCS Administrative Assistant (Janise.Schwee@nrc.gov)
RIV Public Affairs Officer (Victor.Dricks@nrc.gov)
RIV Public Affairs Officer (Lara.Uselding@nrc.gov)
RIV State Liaison Officer (Bill.Maier@nrc.gov)
Project Manager (Fred.Lyon@nrc.gov)
Acting Team Lead, DRS/TSS (Eric.Ruesch@nrc.gov)
Director, DIRS, NRR (Scott.Morris@nrc.gov)
Deputy Director, DIRS, NRR (Allen.Howe@nrc.gov)
Director, DORL, NRR (Anne.Boland@nrc.gov)
Deputy Director, DORL, NRR (George.Wilson@nrc.gov)
Director, NSIR/DPR (Rob.Lewis@nrc.gov)
Chief, LPLIV
-1, DORL, NRR (Michael.Markley@nrc.gov)
Regional Counsel (Karla.Fuller@nrc.gov)
RITS Coordinator (Marisa.Herrera@nrc.gov)
Technical Support Assistant (Loretta.Williams@nrc.gov)
Congressional Affairs Officer (Jenny.Weil@nrc.gov)
RIV Congressional Affairs Officer (Angel.Moreno@nrc.gov)
RIV/ETA: OEDO (Cindy.Rosales
-Cooper@nrc.gov)
ROPassessment Resource@nrc.gov ROPreports@nrc.gov OEMail Resource@nrc.gov Electronic Distribution for Fort Calhoun Station
 
Page 1 of 2 08/26/2015 14:07:16Report 22 UnitNumberPlanned Dates Start EndInspection ActivityTitleNo. of Staff on SiteFort CalhounInspection / Activity Plan 07/01/2015
-06/30/2017EXAM-INITIAL OPERATOR EXAM 41 INITIAL EXAM FC(02/2015)
X0254411/16/201511/20/2015 1 INITIAL EXAM FC(02/2015)
X0254412/14/2015 12/18/2015FCSSIT06-SPECIAL INSPECTION FOR AFW VALVES 21 IPFollowup of Events and Notices of Enforcement Discretion7115306/29/2015 09/01/2015 EP-2-HAB EXERCISE INSPECTION 51 IPEmergency Action Level and Emergency Plan Changes711140408/03/2015 08/07/2015 1 IPExercise Evaluation - Hostile Action (HA) Event711140708/03/2015 08/07/2015 EP-3-EP PERFORMANCE INDICATORS 21 IPDrill/Exercise Performance71151-EP01 08/03/2015 08/07/2015 1 IPERO Readiness71151-EP02 08/03/2015 08/07/2015 1 IPAlert & Notification System Reliability71151-EP03 08/03/2015 08/07/2015 ISFSI-ROUTINE INSPECTION (1 WEEK IN THE MONTH)
11 IPOperation Of An ISFSI 6085509/01/2015 09/30/2015 EB2-05T-TRIENNIAL FIRE PROTECTION INSPECTION 51 IPFire Protection - NFPA 805 (Triennial)7111105X10/19/2015 10/23/2015 1 IPFire Protection - NFPA 805 (Triennial)7111105X11/02/201511/06/2015 RS 24-RADIATION SAFETY 21 IPOccupational ALARA Planning and Controls71124.0211/16/201511/20/2015 1 IPOccupational Dose Assessment71124.0411/16/201511/20/2015TSB 52B-BIENNIAL PI&R INSPECTION 41 IPProblem Identification and Resolution71152B11/16/201511/20/2015 1 IPProblem Identification and Resolution71152B12/07/201512/11/2015 INSP-BIENNIAL REQUAL INSPECTION 21 IPLicensed Operator Requalification Program7111111B06/27/2016 07/01/2016 RS 5678-RADIATION SAFETY - TEAM 41 IPRadiation Monitoring Instrumentation71124.0507/18/2016 07/22/2016 1 IPRadioactive Gaseous and Liquid Effluent Treatment71124.0607/18/2016 07/22/2016 1 IPRadiological Environmental Monitoring Program71124.0707/18/2016 07/22/2016 1 IPRadioactive Solid Waste Processing and Radioactive Material Handling, Storage, and Transportation71124.0807/18/2016 07/22/2016 EB1-17T-FCS PERM PLANT MODS & 50.59 INSPECTION 31 IPEvaluations of Changes, Tests, and Experiments and Permanent Plant Modifications7111117T07/25/2016 08/12/2016 This report does not include INPO and OUTAGE activities. This report shows only on-site and announced inspection procedures.


Page 2 of 208/26/201514:07:16Report 22UnitNumberPlanned DatesStart EndInspection ActivityTitleNo. of Staffon SiteFort CalhounInspection / Activity Plan07/01/2015-06/30/2017EP-1-EP PERFORMANCE INDICATORS11 IPDrill/Exercise Performance71151-EP0110/03/201610/07/20161 IPERO Readiness71151-EP0210/03/201610/07/20161 IPAlert & Notification System Reliability71151-EP0310/03/201610/07/2016EP-2-BIENNIAL EP PROGRAM INSPECTION11 IPAlert and Notification System Testing711140210/03/201610/07/20161 IPEmergency Preparedness Organization Staffing and Augmentation System711140310/03/201610/07/20161 IPEmergency Action Level and Emergency Plan Changes711140410/03/201610/07/20161 IPCorrection of Emergency Preparedness Weaknesses and Deficiencies711140510/03/201610/07/2016RS 12 PI-RADIATION SAFETY21 IPRadiological Hazard Assessment and Exposure Controls71124.0110/03/201610/07/20161 IPOccupational ALARA Planning and Controls71124.0210/03/201610/07/20161 IPOccupational Exposure Control Effectiveness71151-OR0110/03/201610/07/20161 IPRETS/ODCM Radiological Effluent Occurrences71151-PR0110/03/201610/07/201671111.08-INSERVICE INSPECTION11 IPInservice Inspection Activities - PWR7111108P10/03/201610/14/2016RS 13 PI-RADIATION SAFETY21 IPRadiological Hazard Assessment and Exposure Controls71124.0103/27/201703/31/20171 IPIn-Plant Airborne Radioactivity Control and Mitigation71124.0303/27/201703/31/20171 IPOccupational Exposure Control Effectiveness71151-OR0103/27/201703/31/20171 IPRETS/ODCM Radiological Effluent Occurrences71151-PR0103/27/201703/31/2017EB1-07T-FCS HEAT SINK PERFORMANCE11 IPHeat Sink Performance7111107T05/22/201705/26/2017RS 24-RADIATION SAFETY21 IPOccupational ALARA Planning and Controls71124.0206/12/201706/16/20171 IPOccupational Dose Assessment71124.0406/12/201706/16/2017This report does not include INPO and OUTAGE activities. This report shows only on-site and announced inspection procedures.
Page 2 of 2 08/26/2015 14:07:16Report 22 UnitNumberPlanned Dates Start EndInspection ActivityTitleNo. of Staff on SiteFort CalhounInspection / Activity Plan 07/01/2015
-06/30/2017 EP-1-EP PERFORMANCE INDICATORS 11 IPDrill/Exercise Performance71151-EP01 10/03/2016 10/07/2016 1 IPERO Readiness71151-EP02 10/03/2016 10/07/2016 1 IPAlert & Notification System Reliability71151-EP03 10/03/2016 10/07/2016 EP-2-BIENNIAL EP PROGRAM INSPECTION 11 IPAlert and Notification System Testing711140210/03/2016 10/07/2016 1 IPEmergency Preparedness Organization Staffing and Augmentation System711140310/03/2016 10/07/2016 1 IPEmergency Action Level and Emergency Plan Changes711140410/03/2016 10/07/2016 1 IPCorrection of Emergency Preparedness Weaknesses and Deficiencies711140510/03/2016 10/07/2016 RS 12 PI-RADIATION SAFETY 21 IPRadiological Hazard Assessment and Exposure Controls71124.0110/03/2016 10/07/2016 1 IPOccupational ALARA Planning and Controls71124.0210/03/2016 10/07/2016 1 IPOccupational Exposure Control Effectiveness71151-OR01 10/03/2016 10/07/2016 1 IPRETS/ODCM Radiological Effluent Occurrences71151-PR01 10/03/2016 10/07/201671111.08-INSERVICE INSPECTION 11 IPInservice Inspection Activities - PWR7111108P10/03/2016 10/14/2016 RS 13 PI-RADIATION SAFETY 21 IPRadiological Hazard Assessment and Exposure Controls71124.0103/27/2017 03/31/2017 1 IPIn-Plant Airborne Radioactivity Control and Mitigation71124.0303/27/2017 03/31/2017 1 IPOccupational Exposure Control Effectiveness71151-OR01 03/27/2017 03/31/2017 1 IPRETS/ODCM Radiological Effluent Occurrences71151-PR01 03/27/2017 03/31/2017 EB1-07T-FCS HEAT SINK PERFORMANCE 11 IPHeat Sink Performance7111107T05/22/2017 05/26/2017 RS 24-RADIATION SAFETY 21 IPOccupational ALARA Planning and Controls71124.0206/12/2017 06/16/2017 1 IPOccupational Dose Assessment71124.0406/12/2017 06/16/2017 This report does not include INPO and OUTAGE activities. This report shows only on-site and announced inspection procedures.
}}
}}

Revision as of 21:42, 30 June 2018

Mid-Cycle Assessment Letter for Fort Calhoun Station (Report 05000285/2015005)
ML15243A581
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 09/01/2015
From: Miller G B
NRC/RGN-IV/DRP/RPB-D
To: Cortopassi L P
Omaha Public Power District
Geoffrey Miller
References
IR 2015005
Download: ML15243A581 (7)
v • d • e


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION REGION IV 1600 E LAMAR BLVD ARLINGTON, TX 76011

-4511 September 1, 2015 Louis P. Cortopassi, Site Vice President Omaha Public Power District Fort Calhoun Station P.O. Box 550 Fort Calhoun, NE 68023

-0550 Subject: MID-CYCLE ASSESSMENT LETTER FOR FORT CALHOUN STATION (REPORT 05000285/201500 5)

Dear Mr. Cortopassi:

On August 13

, 2015, the Nuclear Regulatory Commission (

NRC) completed its mid

-cycle performance review of the Fort Calhoun Station

. The NRC reviewed the most

-recent quarterly performance indicators (PIs)

, inspection results

, and enforcement actions from July 1, 2014, through June 30, 2015. This letter informs you of the NRC's assessment of your facility during this period and its plans for future inspections at your facility. The NRC determined that overall, the Fort Calhoun Station operated in a manner that preserved public health and safety and met all cornerstone objectives.

The NRC determined the performance at Fort Calhoun Station during the most recent quarter was within the Licensee Response Column of the NRC

's Reactor Oversight Process (ROP) Action Matrix because all inspection findings had very low (i.e., Green) safety significance, and all PIs indicated that your performance was within the nominal, expected range (i.e., Green). Therefore, the NRC plans to conduct ROP baseline inspections at your facility.

By letter dated March 30, 2015, (ADAMS Accession No. ML15089A085), the NRC informed you of the transition of regulatory oversight of Fort Calhoun Station from the Inspection Manual Chapter 0350 "Oversight of Operating Reactor Facilities in an Extended Shutdown as a Result of Significant Performance Problems," process to the Inspection Manual Chapter 0305, "Operating Reactor Assessment Program," oversight process. This transition became effective on April 1, 2015. Based on plant performance at the time, Fort Calhoun Station was placed in the Licensee Response Column of the ROP Action Matrix.

During this mid-cycle performance review, the NRC identified a cross

-cutting theme in Human Performance involving Conservative Bias (H.14), with seven findings with this cross

-cutting aspect identified over the twelve

-month assessment period. The NRC also identified a cross

-cutting theme in Problem Identification and Resolution associated with Evaluation (P.2),

which also consisted of seven findings with this cross

-cutting aspect identified over the twelve

-month assessment period.

In addition, the NRC identified overall cross

-cutting themes in both the Human Performance and Problem Identification and Resolution areas, with 32 and 12 findings

, respectively

, with cross

-cutting aspects in these areas.

After consultation between Region IV and the Division of Regional Inspection Support in the Office of Nuclear Reactor Regulation, the NRC determined that this is the first assessment letter to identify these cross

-cutting themes at Fort Calhoun Station. Therefore, the NRC has only documented the themes in this letter. If these themes continue through the next assessment period, the NRC will evaluate the effectiveness of your actions to address the m to determine whether additional NRC follow

-up should be accomplished, as described in Section 14.02 of Inspection Manual Chapter 0305, "Operating Reactor Assessment Program."

From July 1, 2014, to June 30, 2015, the NRC issued six Severity Level IV traditional enforcement violations associated with impeding the regulatory process, four of which involved the implementation of the 10 CFR 50.59 process. Therefore, the NRC plans to conduct Inspection Procedure 92723, "Follow

-Up Inspection for Three or More Severity Level IV Traditional Enforcement Violations in the Same Area in a 12

-Month Period," to follow

-up on these violations

. The enclosed inspection plan lists the inspections scheduled through June 30, 2017. Routine inspections performed by resident inspectors are not included in the inspection plan. The inspections listed during the second half of the inspection plan are tentative and may be revised at the end

-of-cycle performance review. The NRC provides the inspection plan to allow for the resolution of any scheduling conflicts and personnel availability issues. If circumstances warrant any changes to the inspection plan, the NRC will discuss those changes with you as soon as possible. This inspection plan does not include security related inspections, which will be sent via separate, non

-publicly available correspondence.

In addition, to monitor your continuing efforts to sustain improved plant performance and comply with the commitments identified in our December 17, 2013 Confirmatory Action Letter EA

-13-243 (ADAMS ML13351A395)

, NRC inspections will be conducted for the remaining open items in coordination with their completion.

In response to the accident at Fukushima, the Commission issued Order EA

-12-049, "Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond

-Design-Basis External Events," which requires licensees to develop, implement, and maintain guidance and strategies to maintain or restore core cooling, containment, and spent fuel pool cooling capabilities following a beyond

-design-basis external event. Additionally, the Commission issued Order EA

-12-051, "Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation," which requires licensees to have a reliable means of remotely monitoring wide-range Spent Fuel Pool levels to support effective prioritization of event mitigation and recovery actions in the event of a beyond

-design-basis external event. The NRC is conducting audits of licensee efforts towards compliance with these Orders. This audit includes an onsite component in order for the NRC to evaluate licensee plans for complying with the Orders, as described in site

-specific submittals, and to receive and review information relative to associated open items.

This onsite activity will occur in the months prior to a declaration of compliance for the site, and will aid staff in development of a Final Safety Evaluation for the site.

The date for the onsite component at your site is being coordinated with your staff.

To allow sufficient time for preparations

, a site-specific audit plan for the visit will be provided in advance

. In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390 of the NRC

's "Rules of Practice,

" a copy of this letter will be 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

). Please contact me at 817-200-1173 with any questions you have regarding this letter.

Sincerely,/RA/ Geoffrey B. Miller Chief, Project Branch D Division of Reactor Projects Docket: 50

-285 License: DPR

-40

Enclosure:

Fort Calhoun Station Inspection/Activity Plan In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390 of the NRC's "Rules of Practice," a copy of this letter will be 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

). Please contact me at 817-200-1173 with any questions you have regarding this letter.

Sincerely,/RA/ Geoffrey B. Miller Chief, Project Branch D Division of Reactor Projects Docket: 50

-285 License: DPR

-40

Enclosure:

Fort Calhoun Station Inspection/Activity Plan DISTRIBUTION: See next page ADAMS Accession No. SUNSI Review By: GBM ADAMS Yes No Non-Sensitive Sensitive Publicly Available Non-Publicly Available OFFICE C:DRP/D D:DRS D:DRP NAME GMiller AVegel TPruett SIGNATURE

/RA/ /RA/ /RA/ DATE 8/27/15 8/27/15 8/27/15 Letter to Louis from Geoffrey B. Miller dated September 1, 2015 Subject: MID-CYCLE ASSESSMENT LETTER FOR FORT CALHOUN STATION (REPORT 05000285/201500 5)

DISTRIBUTION

Regional Administrator (Marc.Dapas@nrc.gov)

Deputy Regional Administrator (Kriss.Kennedy@nrc.gov) DRP Director (Troy.Pruett@nrc.gov)

DRP Deputy Director (Ryan.Lantz@nrc.gov)

DRS Director (Anton.Vegel@nrc.gov)

DRS Deputy Director (Jeff.Clark@nrc.gov)

RIV Branch Chief, DRP/D (Geoffrey.Miller@nrc.gov)

Senior Resident Inspector (Max.Schneider@nrc.gov)

Resident Inspector (Brian.Cummings@nrc.gov)

Senior Project Engineer, DRP/

D (Bob.Hagar@nrc.gov)

FCS Administrative Assistant (Janise.Schwee@nrc.gov)

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

RIV Public Affairs Officer (Lara.Uselding@nrc.gov)

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

Project Manager (Fred.Lyon@nrc.gov)

Acting Team Lead, DRS/TSS (Eric.Ruesch@nrc.gov)

Director, DIRS, NRR (Scott.Morris@nrc.gov)

Deputy Director, DIRS, NRR (Allen.Howe@nrc.gov)

Director, DORL, NRR (Anne.Boland@nrc.gov)

Deputy Director, DORL, NRR (George.Wilson@nrc.gov)

Director, NSIR/DPR (Rob.Lewis@nrc.gov)

Chief, LPLIV

-1, DORL, NRR (Michael.Markley@nrc.gov)

Regional Counsel (Karla.Fuller@nrc.gov)

RITS Coordinator (Marisa.Herrera@nrc.gov)

Technical Support Assistant (Loretta.Williams@nrc.gov)

Congressional Affairs Officer (Jenny.Weil@nrc.gov)

RIV Congressional Affairs Officer (Angel.Moreno@nrc.gov)

RIV/ETA: OEDO (Cindy.Rosales

-Cooper@nrc.gov)

ROPassessment Resource@nrc.gov ROPreports@nrc.gov OEMail Resource@nrc.gov Electronic Distribution for Fort Calhoun Station

Page 1 of 2 08/26/2015 14:07:16Report 22 UnitNumberPlanned Dates Start EndInspection ActivityTitleNo. of Staff on SiteFort CalhounInspection / Activity Plan 07/01/2015

-06/30/2017EXAM-INITIAL OPERATOR EXAM 41 INITIAL EXAM FC(02/2015)

X0254411/16/201511/20/2015 1 INITIAL EXAM FC(02/2015)

X0254412/14/2015 12/18/2015FCSSIT06-SPECIAL INSPECTION FOR AFW VALVES 21 IPFollowup of Events and Notices of Enforcement Discretion7115306/29/2015 09/01/2015 EP-2-HAB EXERCISE INSPECTION 51 IPEmergency Action Level and Emergency Plan Changes711140408/03/2015 08/07/2015 1 IPExercise Evaluation - Hostile Action (HA) Event711140708/03/2015 08/07/2015 EP-3-EP PERFORMANCE INDICATORS 21 IPDrill/Exercise Performance71151-EP01 08/03/2015 08/07/2015 1 IPERO Readiness71151-EP02 08/03/2015 08/07/2015 1 IPAlert & Notification System Reliability71151-EP03 08/03/2015 08/07/2015 ISFSI-ROUTINE INSPECTION (1 WEEK IN THE MONTH)

11 IPOperation Of An ISFSI 6085509/01/2015 09/30/2015 EB2-05T-TRIENNIAL FIRE PROTECTION INSPECTION 51 IPFire Protection - NFPA 805 (Triennial)7111105X10/19/2015 10/23/2015 1 IPFire Protection - NFPA 805 (Triennial)7111105X11/02/201511/06/2015 RS 24-RADIATION SAFETY 21 IPOccupational ALARA Planning and Controls71124.0211/16/201511/20/2015 1 IPOccupational Dose Assessment71124.0411/16/201511/20/2015TSB 52B-BIENNIAL PI&R INSPECTION 41 IPProblem Identification and Resolution71152B11/16/201511/20/2015 1 IPProblem Identification and Resolution71152B12/07/201512/11/2015 INSP-BIENNIAL REQUAL INSPECTION 21 IPLicensed Operator Requalification Program7111111B06/27/2016 07/01/2016 RS 5678-RADIATION SAFETY - TEAM 41 IPRadiation Monitoring Instrumentation71124.0507/18/2016 07/22/2016 1 IPRadioactive Gaseous and Liquid Effluent Treatment71124.0607/18/2016 07/22/2016 1 IPRadiological Environmental Monitoring Program71124.0707/18/2016 07/22/2016 1 IPRadioactive Solid Waste Processing and Radioactive Material Handling, Storage, and Transportation71124.0807/18/2016 07/22/2016 EB1-17T-FCS PERM PLANT MODS & 50.59 INSPECTION 31 IPEvaluations of Changes, Tests, and Experiments and Permanent Plant Modifications7111117T07/25/2016 08/12/2016 This report does not include INPO and OUTAGE activities. This report shows only on-site and announced inspection procedures.

Page 2 of 2 08/26/2015 14:07:16Report 22 UnitNumberPlanned Dates Start EndInspection ActivityTitleNo. of Staff on SiteFort CalhounInspection / Activity Plan 07/01/2015

-06/30/2017 EP-1-EP PERFORMANCE INDICATORS 11 IPDrill/Exercise Performance71151-EP01 10/03/2016 10/07/2016 1 IPERO Readiness71151-EP02 10/03/2016 10/07/2016 1 IPAlert & Notification System Reliability71151-EP03 10/03/2016 10/07/2016 EP-2-BIENNIAL EP PROGRAM INSPECTION 11 IPAlert and Notification System Testing711140210/03/2016 10/07/2016 1 IPEmergency Preparedness Organization Staffing and Augmentation System711140310/03/2016 10/07/2016 1 IPEmergency Action Level and Emergency Plan Changes711140410/03/2016 10/07/2016 1 IPCorrection of Emergency Preparedness Weaknesses and Deficiencies711140510/03/2016 10/07/2016 RS 12 PI-RADIATION SAFETY 21 IPRadiological Hazard Assessment and Exposure Controls71124.0110/03/2016 10/07/2016 1 IPOccupational ALARA Planning and Controls71124.0210/03/2016 10/07/2016 1 IPOccupational Exposure Control Effectiveness71151-OR01 10/03/2016 10/07/2016 1 IPRETS/ODCM Radiological Effluent Occurrences71151-PR01 10/03/2016 10/07/201671111.08-INSERVICE INSPECTION 11 IPInservice Inspection Activities - PWR7111108P10/03/2016 10/14/2016 RS 13 PI-RADIATION SAFETY 21 IPRadiological Hazard Assessment and Exposure Controls71124.0103/27/2017 03/31/2017 1 IPIn-Plant Airborne Radioactivity Control and Mitigation71124.0303/27/2017 03/31/2017 1 IPOccupational Exposure Control Effectiveness71151-OR01 03/27/2017 03/31/2017 1 IPRETS/ODCM Radiological Effluent Occurrences71151-PR01 03/27/2017 03/31/2017 EB1-07T-FCS HEAT SINK PERFORMANCE 11 IPHeat Sink Performance7111107T05/22/2017 05/26/2017 RS 24-RADIATION SAFETY 21 IPOccupational ALARA Planning and Controls71124.0206/12/2017 06/16/2017 1 IPOccupational Dose Assessment71124.0406/12/2017 06/16/2017 This report does not include INPO and OUTAGE activities. This report shows only on-site and announced inspection procedures.

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