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=Text=
=Text=
{{#Wiki_filter:Omaha Public Power District                                                               May 23, 2014 LICENSEE:       Omaha Public Power District (OPPD)
{{#Wiki_filter:Omaha Public Power District May 23, 2014 LICENSEE:
FACILITY:       Fort Calhoun Station
Omaha Public Power District (OPPD)
FACILITY:
Fort Calhoun Station  


==SUBJECT:==
==SUBJECT:==
==SUMMARY==
==SUMMARY==
OF MAY 13, 2014 MEETING WITH OMAHA PUBLIC POWER DISTRICT On May 13, 2014, a Category 1 meeting was held between the U.S. Nuclear Regulatory Commission (NRC) and Omaha Public Power District (OPPD), at the Omaha Marriott located at 10220 Regency Circle, Omaha, Nebraska.
OF MAY 13, 2014 MEETING WITH OMAHA PUBLIC POWER DISTRICT On May 13, 2014, a Category 1 meeting was held between the U.S. Nuclear Regulatory Commission (NRC) and Omaha Public Power District (OPPD), at the Omaha Marriott located at 10220 Regency Circle, Omaha, Nebraska.
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http://www.nrc.gov/info-finder/reactor/fcs/special-oversight.html.
http://www.nrc.gov/info-finder/reactor/fcs/special-oversight.html.
In accordance with 10 CFR 2.390 of the NRCs Rules of Practice, a copy of this letter and its enclosures will be available electronically for public inspection in the NRCs Public Document Room or from the Publicly Available Records (PARS) component of the NRCs Agency wide Documents Access and Management System (ADAMS). ADAMS is accessible from the Public Electronic Reading Room page of the NRCs public web site at: http://www.nrc.gov/reading-rm/adams.html.
In accordance with 10 CFR 2.390 of the NRCs Rules of Practice, a copy of this letter and its enclosures will be available electronically for public inspection in the NRCs Public Document Room or from the Publicly Available Records (PARS) component of the NRCs Agency wide Documents Access and Management System (ADAMS). ADAMS is accessible from the Public Electronic Reading Room page of the NRCs public web site at: http://www.nrc.gov/reading-rm/adams.html.
CONTACT: Michael Hay, RIV/DRP (817) 200-1147 Docket No.: 50-285 :
CONTACT: Michael Hay, RIV/DRP (817) 200-1147 Docket No.: 50-285 NRC Presentation Slides :
NRC Presentation Slides :
OPPD Presentation Slides  
OPPD Presentation Slides


ML14143A289 SUNSI Review                     ADAMS              Publicly Available          Non-Sensitive Keyword:
SUNSI Review By: MCH ADAMS Yes No Publicly Available Non-Publicly Available Non-Sensitive Sensitive Keyword:
By: MCH                             Yes No         Non-Publicly Available       Sensitive   SUNSI REV Compl.
SUNSI REV Compl.
OFFICE           RIV/C:DRP/F NAME             MCHay:DLL/PBH SIGNATURE       /RA/
OFFICE RIV/C:DRP/F NAME MCHay:DLL/PBH SIGNATURE  
DATE             05/23/14 Omaha Public Power District                 Electronic distribution by RIV:
/RA/
DATE 05/23/14  
 
Omaha Public Power District Electronic distribution by RIV:
RIV Regional Administrator (Marc.Dapas@nrc.gov)
RIV Regional Administrator (Marc.Dapas@nrc.gov)
RIV Deputy Regional Administrator (Steve.Reynolds@nrc.gov)
RIV Deputy Regional Administrator (Steve.Reynolds@nrc.gov)
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NRR Project Manager (Lynnea.Wilkins@nrc.gov)
NRR Project Manager (Lynnea.Wilkins@nrc.gov)
ACES (R4ACES@nrc.gov)
ACES (R4ACES@nrc.gov)
FortCalhounStation PublicMeeting NuclearRegulatoryCommission May13,2014 Omaha,Nebraska 1


===Introductions===
===Introductions===
Fort Calhoun Station Public Meeting
* Welcome
* Welcome Nuclear Regulatory Commission
* IntroductionofNRCpersonnel 2
* Introduction of NRC personnel May 13, 2014 Omaha, Nebraska 1                                                        2 Purpose of Meeting                                          Opening Remarks
PurposeofMeeting
* NRC will present status of regulatory activities
* NRCwillpresentstatusofregulatoryactivities associatedwiththeFortCalhounStation
* Tony Vegel, Director, Division of Reactor Safety associated with the Fort Calhoun Station
* OPPD willpresentdetailsofFortCalhoun Stationperformanceimprovementinitiatives
                                                        - Chair, Fort Calhoun Station Oversight Panel
* Publiccommentsandquestions OpeningRemarks
* OPPD will present details of Fort Calhoun
* TonyVegel,Director,DivisionofReactorSafety
* Louise Lund, Deputy Director, Division of Operating Station performance improvement initiatives          Reactor Licensing
- Chair,FortCalhounStationOversightPanel
                                                        - Vice Chair, Fort Calhoun Station Oversight Panel
* LouiseLund,DeputyDirector,DivisionofOperating ReactorLicensing
* Public comments and questions 4
- ViceChair,FortCalhounStationOversightPanel 4
Enclosure 1
PostRestartCAL OPPDcommittedtotheNRCtocontinue implementingimprovementinitiativesinkey areasandaddressspecifictechnicalitems 5
NRCActionsCompleted
* NRCissuedPostRestartConfirmatoryAction LetterDecember17,2013
- Keyareasforsustainedperformanceimprovement
* HumanPerformance
* SafetyCulture
* CorrectiveActionProcess
* DesignBasisReconstitution 6
NRCAssessmentActivities
* Routineinspections
- ResidentInspectors
- Regionalinspections
* Teaminspection(Summer2014)
- AssessCorrectiveActionProcesseffectiveness
- AssessPostRestartConfirmatoryActionLetter items 7
InSummary
* IncreasedNRCoversightactivitiesremain
* NRCcontinuestoimplementindependentand thoroughinspectionactivitiestoassessstation performanceimprovementprogress 8
OPPDPresentation 9
ContactingtheNRC
* Reportanemergency
- (301)8165100(callcollect)
* Reportasafetyconcern
- (800)6957403
- Allegation@nrc.gov
* Generalinformationorquestions
- www.nrc.gov 10 11


PostRestart CAL                                    NRC Actions Completed
1 OPPDs Fort Calhoun Station Driving To Excellence Public meeting with the U.S. Nuclear Regulatory Commission May 13, 2014 2
* NRC issued PostRestart Confirmatory Action OPPD committed to the NRC to continue                    Letter December 17, 2013 implementing improvement initiatives in key              - Key areas for sustained performance improvement
* Plant Status
* Human Performance areas and address specific technical items
* Problem Identification and Resolution
* Safety Culture
* Corrective Action Process
* Design Basis Reconstitution 5                                                        6 NRC Assessment Activities                                            In Summary
* Routine inspections
* Increased NRC oversight activities remain
  - Resident Inspectors
  - Regional inspections
* Team inspection (Summer 2014)
* NRC continues to implement independent and
  - Assess Corrective Action Process effectiveness    thorough inspection activities to assess station
  - Assess PostRestart Confirmatory Action Letter    performance improvement progress items 7                                                        8 Enclosure 1
 
OPPD Presentation                      Contacting the NRC
* Report an emergency
                        - (301) 8165100 (call collect)
* Report a safety concern
                        - (800) 6957403
                        - Allegation@nrc.gov
* General information or questions
                        - www.nrc.gov 9                                        10 11 Enclosure 1
 
Topics for Discussion OPPDs Fort Calhoun Station
* Plant Status Driving To Excellence
* Problem Identification and Resolution Public meeting with the U.S. Nuclear Regulatory Commission
* Engineering Products
* Engineering Products
* Design and Licensing Basis Control and Use
* Design and Licensing Basis Control and Use
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* Integration
* Integration
* Nuclear Oversight
* Nuclear Oversight
* Closing Remarks May 13, 2014 1                                                                2 Plant Status                                                  Plant Status Sitewide Industrial Safety                                 Sitewide Human Performance Injury Comparison Summary                 2013     2014 2014 Sitewide Clock Reset:
* Closing Remarks Topics for Discussion 3
Untreated Injuries:                         11       3                                       March 17: Stator water First Aid Injuries:                         15       0                                       cooling leak caused an automatic trip of the unit Occupational Safety and Health 4      0 Administration (OSHA) Recordable:
Plant Status Sitewide Industrial Safety Injury Comparison Summary 2013 2014 Untreated Injuries:
Industry best is in the Lost-Time / Restricted:                       4       0                                       range of 0 to 2 sitewide clock resets per year 3                                                                4 Enclosure 2
11 3
First Aid Injuries:
15 0
Occupational Safety and Health Administration (OSHA) Recordable:
4 0
Lost-Time / Restricted:
4 0
4 Plant Status Industry best is in the range of 0 to 2 sitewide clock resets per year Sitewide Human Performance 2014 Sitewide Clock Reset:
March 17: Stator water cooling leak caused an automatic trip of the unit


Plant Status                                                                                         Plant Status Department-Level Human Performance                                                                                   Capacity Factor 140 100 120 90 100                                                                                          80
5 134 58 41 8
                                          ** Department-Level Performance Goals               70 80                                                                                                                                                                        93.2%
8 0
Percent
20 40 60 80 100 120 140 2011 2012 2013
* 2014 Year-to-Date 134                                                                                60 60 50 since 40 61                                                                       40 restart 58                                                                        30 20                            41 6*            8              8                    20 0                                                                                                Dec-13   Jan-14   Feb-14   Mar-14   Apr-14   May-14   Jun-14   Jul-14   Aug-14   Sep-14   Oct-14   Nov-14   Dec-14 2011    2012      2013      *2014        **2015        **2016                        Historical Data       Site Performance         Goal           Industry Top Quartile       Year End Projection Industry best is in range of 6 to 12 dept. clock resets per year 5                                                                                      6 Plant Status                                           Problem Identification and Resolution
*2014
* Corrective Action Program (CAP) changes implemented to Operational Challenges                                                              improve OPPDs detection and correction of plant issues
**2015
* Shut down due to maintenance                                                              - Provide an updated status of actions and effectiveness reviews evolution on stator water system
**2016 6*
Plant Status Industry best is in range of 6 to 12 dept. clock resets per year Department-Level Human Performance
** Department-Level Performance Goals
* 2014 Year-to-Date 61 6
Plant Status Capacity Factor 20 30 40 50 60 70 80 90 100 Dec-13 Jan-14 Feb-14 Mar-14 Apr-14 May-14 Jun-14 Jul-14 Aug-14 Sep-14 Oct-14 Nov-14 Dec-14 Percent Historical Data Site Performance Goal Industry Top Quartile Year End Projection 93.2%
since restart 7
Operational Challenges
* Shut down due to maintenance evolution on stator water system
* Down power due to VA-46 Control Room Air Conditioning Units Plant Status 8
* Corrective Action Program (CAP) changes implemented to improve OPPDs detection and correction of plant issues
- Provide an updated status of actions and effectiveness reviews
* Results
* Results
* Down power due to VA-46 Control                                                          - Focused area self-assessment insights Room Air Conditioning Units
- Focused area self-assessment insights
                                                                                            - Performance indicators insights
- Performance indicators insights
                                                                                            - Trending insights
- Trending insights
                                                                                            - Areas providing challenges and actions to address 7                                                                                      8 Enclosure 2
- Areas providing challenges and actions to address Problem Identification and Resolution


Engineering CAP Health: March 2013 - March 2014 Comparison Engineering  Engineering Engineering Products M arch 2013  M arch 2014 Coding and Event Code Backlog (1 month)
9
Analysis Number of CRs Coded w ith Adverse Trend (1 month)
* Observations and trends for:
* Observations and trends for:                                                                 (trending) Cause Code Backlog (1 month)                                                            1            0 Overall            Number of Significant Events (1 year)
- Corrective Action Products
        - Corrective Action Products Number of CRs Identified (1 month)                                                  392          124 Identification
- Quality of Engineering Products
        - Quality of Engineering Products                                                           and        3 Month Engagement Ratio                                                            65%         66%
- Operability Evaluations
Screening Self-Identification Ratio - Level 1,2,3 CRs (1 month)                                  42%         74%
- Reportability Determinations Engineering Products Engineering M arch 2013 Engineering M arch 2014 1
Meetings
0 Overall 392 124 65%
        - Operability Evaluations                                                                              Number of CAP Meeting Observations (1 month)                                          4            0 Number of Repeat Events (1 year)                                              1            0
66%
        - Reportability Determinations                                                                                Number of Ineffective Effective Review s for Root Causes Only (1 month)        0           0 DCARB RCA Rejection Rate (3 month avg.)                                       0%          0%
42%
DCARB ACA (Tier 1) Rejection Rate (3 month avg.)                             29%        20%
74%
Analysis            DCARB ACA (Tier 2) Rejection Rate (3 month avg.)                             58%        13%
4 0
RCA Rejection Rate (3 month avg.)                                             57%          0%
1 0
ACA (Tier 1) Rejection Rate (3 month avg.)                                   0%          0%
0 0
DCARB CR Closure Rejection Rate (3 month avg.)                               30%        15%
0%
9                                                                                            10 MRC CR Closure Rejection Rate (3 month avg.)                                 50%        25%
0%
Engineering CAP Health: March 2013 - March 2014 Comparison Engineering  Engineering M arch 2013   M arch 2014 Overdue Priorities (1 month)                             47            7 Number of Overdue Non-ACA and Non-RCA REs (1 month)       9            0 Number of Overdue Corrective Actions (3 month total)                                                                     Closure Rate for Engineering of Active Action items A, B, C 9            7                                4000 Number of Overdue Simple Causes (1 month)                  8            0                                3500 Average Time to Perform RCAs (12 month avg.)             151            83                                3000 Number of Average Time to Perform Tier 1 ACAs (1 month avg.)       252          380                                2500 Average Time to Perform Tier 2 ACAs (1 month)           241            68                                2000 Action items Average Time to Perform Simple Causes (1 month)           15            15                                1500 Median Age of Open Non-Outage AIs (days) (1 month)       965          1,148 Timeliness                                                                                                            1000 Number of Open Non-Outage AIs > 365 days (1 month)       212          733                                500 Oldest Open Non-Outage AI (days) (1 month)             1,930        2,294                                0 Number of Open Outage-Related AIs (1 month)             261          124 Dec13            Jan14          Feb14          Mar14          Apr14 Number of Open CAPR's (1 month)                           26            15                  Number of AC Actions              3,683            3,459            3,230            2,652          2,374 Number of Open CA's (1 month)                           1,785        1,270 Number of Open RE's (1 month)                           465          144 Median Age of Open RA's (days) (1 month)                 774          956 Number of Open RA's > 365 days (1 month)                 320          321 11                                                                                                       12 CRs in Ready to Close (1 month)                          917          497 Enclosure 2
29%
20%
58%
13%
57%
0%
0%
0%
30%
15%
50%
25%
Engineering CAP Health: March 2013 - March 2014 Comparison MRC CR Closure Rejection Rate (3 month avg.)
DCARB CR Closure Rejection Rate (3 month avg.)
DCARB ACA (Tier 1) Rejection Rate (3 month avg.)
RCA Rejection Rate (3 month avg.)
Number of Ineffective Effective Review s for Root Causes Only (1 month)
Number of CAP Meeting Observations (1 month)
Analysis Number of Repeat Events (1 year)
DCARB RCA Rejection Rate (3 month avg.)
DCARB ACA (Tier 2) Rejection Rate (3 month avg.)
ACA (Tier 1) Rejection Rate (3 month avg.)
Number of Significant Events (1 year)
Identification and Screening Meetings Number of CRs Identified (1 month)
Self-Identification Ratio - Level 1,2,3 CRs (1 month) 3 Month Engagement Ratio Coding and Analysis (trending)
Event Code Backlog (1 month)
Cause Code Backlog (1 month)
Number of CRs Coded w ith Adverse Trend (1 month) 10 Engineering M arch 2013 Engineering M arch 2014 47 7
9 0
9 7
8 0
151 83 252 380 241 68 15 15 965 1,148 212 733 1,930 2,294 261 124 26 15 1,785 1,270 465 144 774 956 320 321 917 497 Timeliness Overdue Priorities (1 month)
Number of Overdue Non-ACA and Non-RCA REs (1 month)
Number of Overdue Corrective Actions (3 month total)
Average Time to Perform RCAs (12 month avg.)
Number of Overdue Simple Causes (1 month)
Average Time to Perform Tier 2 ACAs (1 month)
Average Time to Perform Tier 1 ACAs (1 month avg.)
Median Age of Open Non-Outage AIs (days) (1 month)
Average Time to Perform Simple Causes (1 month)
Oldest Open Non-Outage AI (days) (1 month)
Number of Open Non-Outage AIs > 365 days (1 month)
Number of Open CA's (1 month)
Number of Open CAPR's (1 month)
Number of Open Outage-Related AIs (1 month)
Engineering CAP Health: March 2013 - March 2014 Comparison CRs in Ready to Close (1 month)
Number of Open RA's > 365 days (1 month)
Median Age of Open RA's (days) (1 month)
Number of Open RE's (1 month) 11 12 0
500 1000 1500 2000 2500 3000 3500 4000 Number of Action items Dec13 Jan14 Feb14 Mar14 Apr14 Number of AC Actions 3,683 3,459 3,230 2,652 2,374 Closure Rate for Engineering of Active Action items A, B, C


Engineering Products                                                                                                        Engineering Assurance Group Products 2013-2014 Comparison 120.00%
13
* Observations and trends for:
* Observations and trends for:
- Corrective Action Products
- Quality of Engineering Products
- Operability Evaluations
- Reportability Determinations Engineering Products 14 50.59 Screens Applicability Determinations Applicability Determinations 72.48 Screens Engineering Products Immediate Operability Determinations Operability Evaluations Reportability Evaluations 50.59 Evaluations Total Percent Accepted 2013 82.80%
94.29%
98.53%
90.75%
98.00%
70.30%
80.43%
78.38%
94.87%
Percent Accepted 2014 100.00%
96.55%
96.43%
92.31%
98.49%
66.67%
81.25%
0 97.56%
0.00%
20.00%
40.00%
60.00%
80.00%
100.00%
100.00%
Percent of Accepted EAG Products
120.00%
  - Corrective Action Products 80.00%
Percent of Accepted EAG Products Engineering Assurance Group Products 2013-2014 Comparison 15 Design and Licensing Basis Control and Use
  - Quality of Engineering Products 60.00%
  - Operability Evaluations                                                                                                          40.00%
  - Reportability Determinations                                                                                                    20.00%
0.00%
Applicability                  Immediate Applicability                    Engineering                   Operability  Reportability    50.59 50.59 Screens                    Determinations                  Operability                                                  Total Determinations                    Products                     Evaluations  Evaluations    Evaluations 72.48 Screens                  Determinations Percent Accepted 82.80%          94.29%          98.53%          90.75%        98.00%        70.30%        80.43%        78.38%      94.87%
2013 Percent Accepted 100.00%          96.55%          96.43%          92.31%        98.49%        66.67%        81.25%            0        97.56%
2014 13                                                                                                                                  14 Design and Licensing Basis                                                                                                           Design and Licensing Basis Control and Use                                                                                                                      Control and Use
* OPPDs post-restart commitment states:
* OPPDs post-restart commitment states:
- After restart, OPPD will complete a significant effort to perform a risk-focused reconstitution of the:
Design basis, Licensing basis, and Updated Safety Analysis Report
- As part of this project, OPPD will:
Ensure proper classification of equipment, Convert to a safety-related Q List approach for equipment classification, and Complete a key calculation review
- A pilot program will be completed during 2014 on a selected system to check & adjust the process, scheduling and resource allocation
- Complete the reconstitution project before the end of the 4th quarter, 2018 15 16 Design and Licensing Basis Control and Use
* Project Activities Completed or In Progress
* Project Activities Completed or In Progress
  - After restart, OPPD will complete a significant effort to perform a risk-                                                        - January 2014 - Commenced drafting project request for proposal focused reconstitution of the:                                                                                                    (COMPLETE)
- January 2014 - Commenced drafting project request for proposal (COMPLETE)
Design basis,                                                                                                              - February 7, 2014 - Issue project request for proposal to vendors Licensing basis, and                                                                                                          (COMPLETE)
- February 7, 2014 - Issue project request for proposal to vendors (COMPLETE)
Updated Safety Analysis Report                                                                                              - March 28, 2014 - Vendor proposals due (COMPLETE)
- March 28, 2014 - Vendor proposals due (COMPLETE)
  - As part of this project, OPPD will:                                                                                              - April 30, 2014 - Award project contract (COMPLETE)
- April 30, 2014 - Award project contract (COMPLETE)
Ensure proper classification of equipment,                                                                                  - May 5, 2014 - Commence project (COMPLETE)
- May 5, 2014 - Commence project (COMPLETE)
Convert to a safety-related Q List approach for equipment classification, and Complete a key calculation review
- January 2014: Commenced review of key calculations Pre-restart 93 calculations were reviewed, with 45 revisions recommended 330 of 382 key calculations have been reviewed with 147 revisions recommended Calculation issues identified to date have been determined to be not consequential, but calculations must be brought up to todays standards 16  
                                                                                                                                      - January 2014: Commenced review of key calculations
  - A pilot program will be completed during 2014 on a selected system                                                                        Pre-restart 93 calculations were reviewed, with 45 revisions recommended to check & adjust the process, scheduling and resource allocation                                                                        330 of 382 key calculations have been reviewed with 147 revisions recommended
  - Complete the reconstitution project before the end of the                                                                                  Calculation issues identified to date have been determined to be not 4th quarter, 2018                                                                                                                          consequential, but calculations must be brought up to todays standards 15                                                                                  15                                            16                                                                                                                                        16 Enclosure 2


Design and Licensing Basis                                                           Design and Licensing Basis Control and Use                                                                      Control and Use
17 Design and Licensing Basis Control and Use
* Project Activities to be Completed
* Project Activities to be Completed
- June 30, 2014 - Complete Phase 1 (Develop project processes/procedures)
- December 31, 2014 - Complete Phase 2 (Pilot program - NRC commitment)
- February 1, 2015 - Complete project status assessment Approximately every six months between Feb. 1, 2015, and Dec. 31, 2018 -
Perform project status assessments
- February 28, 2015 - Complete Phase 3 (Incorporate lessons learned from pilot program)
- December 31, 2018 - Complete Phase 4 (Complete reconstitution project - NRC commitment)
- February 1, 2019 - Complete project final effectiveness review 17 18 Design and Licensing Basis Control and Use
* Project Oversight
* Project Oversight
  - June 30, 2014 - Complete Phase 1 (Develop project processes/procedures)                                                              - Oversight to be provided as follows:
- Oversight to be provided as follows:
  - December 31, 2014 - Complete Phase 2 (Pilot program - NRC
* OPPD project manager who is independent of the production work
* OPPD project manager who is independent of the production work commitment)
* OPPD/Exelon senior management
* OPPD/Exelon senior management
  - February 1, 2015 - Complete project status assessment Approximately every six months between Feb. 1, 2015, and Dec. 31, 2018 -
* Periodic project status assessments
* Periodic project status assessments Perform project status assessments
* Independent project oversight board
* Independent project oversight board
  - February 28, 2015 - Complete Phase 3 (Incorporate lessons learned from pilot program)
* FCS Nuclear Oversight Department
* FCS Nuclear Oversight Department
  - December 31, 2018 - Complete Phase 4 (Complete reconstitution
* Nuclear Safety Review Board 18 19
* Nuclear Safety Review Board project - NRC commitment)
  - February 1, 2019 - Complete project final effectiveness review 17                                                                              17    18                                                                       18 Containment Internal Structures                                                        Containment Internal Structures
* OPPD committed to:
* OPPD committed to:
Evaluate the structural design margin for the containment internal structure, and reactor cavity and compartments, and resolve any deficiencies in accordance with FCSs CAP Regarding Beams 22A and Beam 22B under Safety Injection Tanks 6B/D, resolve any deficiencies in accordance with the CAP Resolve and correct any deficiencies surrounding the reactor vessel head stand (RVHS) prior to its next use Containment Internal Structures 20
* Resolution strategy for 2015 refueling outage
* Resolution strategy for 2015 refueling outage
  - Evaluate the structural design margin for the containment internal                  - Install columns in the basement of the containment building under structure, and reactor cavity and compartments, and resolve any                      floor Beams 22A and Beam 22B to reduce the loading on the two deficiencies in accordance with FCSs CAP                                            floor beams
- Install columns in the basement of the containment building under floor Beams 22A and Beam 22B to reduce the loading on the two floor beams
  - Regarding Beams 22A and Beam 22B under Safety Injection Tanks                      - Replace the existing RVHS pedestal supports with a structural steel 6B/D, resolve any deficiencies in accordance with the CAP                            box frame that spans the floor and transfers the loads to adjacent
- Replace the existing RVHS pedestal supports with a structural steel box frame that spans the floor and transfers the loads to adjacent walls and columns
  - Resolve and correct any deficiencies surrounding the reactor vessel                    walls and columns head stand (RVHS) prior to its next use                                          - Preliminary design will be complete by third quarter 2014 19                                                                                    20 Enclosure 2
- Preliminary design will be complete by third quarter 2014 Containment Internal Structures


Site Operational Focus         The Exelon Nuclear Management Model Procedures                                                             Integration status
21 Site Operational Focus Procedures
* Procedure focus
* Procedure focus
- Quality
- Use and Adherence
- Level of Detail
* Cornerstone for performance
- Emergency and Abnormal Operations Demonstrated using simulator Upgrades continue
- Normal Operations Support plant operations Require verbatim compliance
- Administrative Station-wide effort 22 Integration status
* More than 4,000 tasks completed
* More than 4,000 tasks completed
      - Quality                                - Design Review Board
- Design Review Board  
      - Use and Adherence                      - Human Performance Fundamentals
- Human Performance Fundamentals
      - Level of Detail                        - Nuclear Oversight Processes
- Nuclear Oversight Processes
* Cornerstone for performance                - Learning Programs
- Learning Programs
      - Emergency and Abnormal                - Operations Standards and Expectations Operations
- Operations Standards and Expectations
* Approximately 8,000 tasks remain, with 6,000 of these Demonstrated using simulator Upgrades continue                scheduled for completion in 2014
* Approximately 8,000 tasks remain, with 6,000 of these scheduled for completion in 2014
      - Normal Operations                      - Weekly integration status meetings to review schedule adherence Support plant operations Require verbatim compliance
- Weekly integration status meetings to review schedule adherence
* Lessons Learned
* Lessons Learned
      - Administrative                        - Data Sharing Station-wide effort                - Gap Analysis 21                                        22 Nuclear Oversight         Flooding Recovery Action Plans Independent Assessment
- Data Sharing
* Five Flooding Recovery Post-Restart Action commitments outlined in Section 2 of the Confirmatory Action Letter (CAL)
- Gap Analysis The Exelon Nuclear Management Model 23 Nuclear Oversight Independent Assessment Plant Observations and Performance 24 Five Flooding Recovery Post-Restart Action commitments outlined in Section 2 of the Confirmatory Action Letter (CAL)
* Three of the Section 2 Flooding Recovery Post-Restart Action commitments have been submitted to the NRC resident inspectors
Three of the Section 2 Flooding Recovery Post-Restart Action commitments have been submitted to the NRC resident inspectors Item 4.4.3.1 - Gather flood response lessons learned through condition report reviews to determine if procedure or strategy changes should be implemented (completed December 12, 2012)
                                              - Item 4.4.3.1 - Gather flood response lessons learned through condition report reviews to determine if procedure or strategy changes should be implemented (completed December 12, 2012)
Item 4.4.3.3 - Implement procedure and strategy changes as indicated by the lessons learned review conducted (completed February 20, 2013)
Plant Observations and Performance    - Item 4.4.3.3 - Implement procedure and strategy changes as indicated by the lessons learned review conducted (completed February 20, 2013)
Item 1.2.3.21 - Inspect tank and equipment on demineralized water tank for damage (completed February 10, 2014)
                                              - Item 1.2.3.21 - Inspect tank and equipment on demineralized water tank for damage (completed February 10, 2014)
Two of the Section 2 Flooding Recovery Post-Restart Action commitments are scheduled Item 4.4.3.2 - Review flood design basis and determine if the 2011 flood event provides additional information that should drive design basis changes Item 1.2.3.82 - Perform independent spent fuel storage installation route load test Flooding Recovery Action Plans
* Two of the Section 2 Flooding Recovery Post-Restart Action commitments are scheduled
 
                                              - Item 4.4.3.2 - Review flood design basis and determine if the 2011 flood event provides additional information that should drive design basis changes
25
                                              - Item 1.2.3.82 - Perform independent spent fuel storage installation route load test 23                                        24 Enclosure 2
* Project scope Flooding reevaluation and seismic evaluation Flooding and seismic walkdowns
 
Results submitted to the NRC
 
Actions ongoing Mitigating strategies for beyond design basis external events Strategy developed and submitted to NRC
 
Portable equipment pre-staged at FCS
 
Procedures (Admin/Operations/PM/Testing)
 
Staffing


Fukushima Response Project                                               Closing Remarks
Communications (internal and external)
* Project scope
Spent Fuel Pool Instrumentation (SFPI)
 
SFPI modifications submitted to the NRC Fukushima Response Project Portable Submersible Pumps 26
* Plant Status
* Plant Status
  - Flooding reevaluation and seismic evaluation    Portable Submersible
* Problem Identification and Resolution
* Problem Identification and Resolution
  - Flooding and seismic walkdowns Results submitted to the NRC Pumps
* Engineering Products
* Engineering Products Actions ongoing
* Design and Licensing Basis Control and Use
* Design and Licensing Basis Control
  - Mitigating strategies for beyond design basis              and Use external events
* Containment Internal Structures
* Containment Internal Structures
  - Strategy developed and submitted to NRC Portable equipment pre-staged at FCS
* Site Operational Focus
* Site Operational Focus Procedures (Admin/Operations/PM/Testing)
* Integration
Staffing
* Integration Communications (internal and external)
* Nuclear Oversight
* Nuclear Oversight
  - Spent Fuel Pool Instrumentation (SFPI)
* Closing Remarks Closing Remarks }}
* Closing Remarks SFPI modifications submitted to the NRC 25                                                              26 Enclosure 2}}

Latest revision as of 20:35, 10 January 2025

May 13, 2014 Summary of Meeting with Omaha Public Power District Presented the Status of Inspection Manual Chapter 0350 Oversight Activities at Fort Calhoun Station
ML14143A289
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 05/23/2014
From: Hay M
NRC/RGN-IV/DRP
To:
Hay M
References
Download: ML14143A289 (13)


Text

Omaha Public Power District May 23, 2014 LICENSEE:

Omaha Public Power District (OPPD)

FACILITY:

Fort Calhoun Station

SUBJECT:

SUMMARY

OF MAY 13, 2014 MEETING WITH OMAHA PUBLIC POWER DISTRICT On May 13, 2014, a Category 1 meeting was held between the U.S. Nuclear Regulatory Commission (NRC) and Omaha Public Power District (OPPD), at the Omaha Marriott located at 10220 Regency Circle, Omaha, Nebraska.

The NRC presented the status of Inspection Manual Chapter 0350 oversight activities at Fort Calhoun Station, and the Omaha Public Power District presented details of their actions for continued performance improvement following the plant restart in December, 2013. The slide presentations are available electronically from the NRCs Agency wide Documents Access and Management System (ADAMS) and are enclosed in this notice. A video of the public meeting will be posted on the web site devoted to the special oversight at Fort Calhoun Station, available at:

http://www.nrc.gov/info-finder/reactor/fcs/special-oversight.html.

In accordance with 10 CFR 2.390 of the NRCs Rules of Practice, a copy of this letter and its enclosures will be available electronically for public inspection in the NRCs Public Document Room or from the Publicly Available Records (PARS) component of the NRCs Agency wide Documents Access and Management System (ADAMS). ADAMS is accessible from the Public Electronic Reading Room page of the NRCs public web site at: http://www.nrc.gov/reading-rm/adams.html.

CONTACT: Michael Hay, RIV/DRP (817) 200-1147 Docket No.: 50-285 NRC Presentation Slides :

OPPD Presentation Slides

SUNSI Review By: MCH ADAMS Yes No Publicly Available Non-Publicly Available Non-Sensitive Sensitive Keyword:

SUNSI REV Compl.

OFFICE RIV/C:DRP/F NAME MCHay:DLL/PBH SIGNATURE

/RA/

DATE 05/23/14

Omaha Public Power District Electronic distribution by RIV:

RIV Regional Administrator (Marc.Dapas@nrc.gov)

RIV Deputy Regional Administrator (Steve.Reynolds@nrc.gov)

RIV DRP Director (Kriss.Kennedy@nrc.gov)

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

RIV DRS Director (Anton.Vegel@nrc.gov)

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

RIV Senior Resident Inspector (John.Kirkland@nrc.gov)

RIV Resident Inspector (Jacob.Wingebachl@nrc.gov)

RIV Branch Chief, DRP/F (Michael.Hay@nrc.gov)

Project Engineer, DRP/F (Chris.Smith@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 Project Manager (Joseph.Sebrosky@nrc.gov)

RIV Branch Chief, DRS/TSB (Geoffrey.Miller@nrc.gov)

RIV RITS Coordinator (Marisa.Herrera@nrc.gov)

RIV Regional Counsel (Karla.Fuller@nrc.gov)

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

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

OEMail Resource OEWEB Resource (Sue.Bogle@nrc.gov)

RIV/ETA: OEDO (Joseph.Nick@nrc.gov)

RIV RSLO (Bill.Maier@nrc.gov)

MC 0350 Panel Vice Chairman (Louise.Lund@nrc.gov)

MC 0350 Panel Member (Michael.Balazik@nrc.gov)

MC 0350 Panel Member (Michael.Markley@nrc.gov)

NRR Project Manager (Lynnea.Wilkins@nrc.gov)

ACES (R4ACES@nrc.gov)

FortCalhounStation PublicMeeting NuclearRegulatoryCommission May13,2014 Omaha,Nebraska 1

Introductions

  • Welcome
  • IntroductionofNRCpersonnel 2

PurposeofMeeting

  • NRCwillpresentstatusofregulatoryactivities associatedwiththeFortCalhounStation
  • OPPD willpresentdetailsofFortCalhoun Stationperformanceimprovementinitiatives
  • Publiccommentsandquestions OpeningRemarks
  • TonyVegel,Director,DivisionofReactorSafety

- Chair,FortCalhounStationOversightPanel

  • LouiseLund,DeputyDirector,DivisionofOperating ReactorLicensing

- ViceChair,FortCalhounStationOversightPanel 4

PostRestartCAL OPPDcommittedtotheNRCtocontinue implementingimprovementinitiativesinkey areasandaddressspecifictechnicalitems 5

NRCActionsCompleted

  • NRCissuedPostRestartConfirmatoryAction LetterDecember17,2013

- Keyareasforsustainedperformanceimprovement

  • HumanPerformance
  • SafetyCulture
  • CorrectiveActionProcess
  • DesignBasisReconstitution 6

NRCAssessmentActivities

  • Routineinspections

- ResidentInspectors

- Regionalinspections

  • Teaminspection(Summer2014)

- AssessCorrectiveActionProcesseffectiveness

- AssessPostRestartConfirmatoryActionLetter items 7

InSummary

  • IncreasedNRCoversightactivitiesremain
  • NRCcontinuestoimplementindependentand thoroughinspectionactivitiestoassessstation performanceimprovementprogress 8

OPPDPresentation 9

ContactingtheNRC

  • Reportanemergency

- (301)8165100(callcollect)

  • Reportasafetyconcern

- (800)6957403

- Allegation@nrc.gov

  • Generalinformationorquestions

- www.nrc.gov 10 11

1 OPPDs Fort Calhoun Station Driving To Excellence Public meeting with the U.S. Nuclear Regulatory Commission May 13, 2014 2

  • Plant Status
  • Problem Identification and Resolution
  • Engineering Products
  • Design and Licensing Basis Control and Use
  • Containment Internal Structures
  • Site Operational Focus
  • Integration
  • Nuclear Oversight
  • Closing Remarks Topics for Discussion 3

Plant Status Sitewide Industrial Safety Injury Comparison Summary 2013 2014 Untreated Injuries:

11 3

First Aid Injuries:

15 0

Occupational Safety and Health Administration (OSHA) Recordable:

4 0

Lost-Time / Restricted:

4 0

4 Plant Status Industry best is in the range of 0 to 2 sitewide clock resets per year Sitewide Human Performance 2014 Sitewide Clock Reset:

March 17: Stator water cooling leak caused an automatic trip of the unit

5 134 58 41 8

8 0

20 40 60 80 100 120 140 2011 2012 2013

  • 2014
    • 2015
    • 2016 6*

Plant Status Industry best is in range of 6 to 12 dept. clock resets per year Department-Level Human Performance

    • Department-Level Performance Goals
  • 2014 Year-to-Date 61 6

Plant Status Capacity Factor 20 30 40 50 60 70 80 90 100 Dec-13 Jan-14 Feb-14 Mar-14 Apr-14 May-14 Jun-14 Jul-14 Aug-14 Sep-14 Oct-14 Nov-14 Dec-14 Percent Historical Data Site Performance Goal Industry Top Quartile Year End Projection 93.2%

since restart 7

Operational Challenges

  • Shut down due to maintenance evolution on stator water system
  • Down power due to VA-46 Control Room Air Conditioning Units Plant Status 8
  • Corrective Action Program (CAP) changes implemented to improve OPPDs detection and correction of plant issues

- Provide an updated status of actions and effectiveness reviews

  • Results

- Focused area self-assessment insights

- Performance indicators insights

- Trending insights

- Areas providing challenges and actions to address Problem Identification and Resolution

9

  • Observations and trends for:

- Corrective Action Products

- Quality of Engineering Products

- Operability Evaluations

- Reportability Determinations Engineering Products Engineering M arch 2013 Engineering M arch 2014 1

0 Overall 392 124 65%

66%

42%

74%

4 0

1 0

0 0

0%

0%

29%

20%

58%

13%

57%

0%

0%

0%

30%

15%

50%

25%

Engineering CAP Health: March 2013 - March 2014 Comparison MRC CR Closure Rejection Rate (3 month avg.)

DCARB CR Closure Rejection Rate (3 month avg.)

DCARB ACA (Tier 1) Rejection Rate (3 month avg.)

RCA Rejection Rate (3 month avg.)

Number of Ineffective Effective Review s for Root Causes Only (1 month)

Number of CAP Meeting Observations (1 month)

Analysis Number of Repeat Events (1 year)

DCARB RCA Rejection Rate (3 month avg.)

DCARB ACA (Tier 2) Rejection Rate (3 month avg.)

ACA (Tier 1) Rejection Rate (3 month avg.)

Number of Significant Events (1 year)

Identification and Screening Meetings Number of CRs Identified (1 month)

Self-Identification Ratio - Level 1,2,3 CRs (1 month) 3 Month Engagement Ratio Coding and Analysis (trending)

Event Code Backlog (1 month)

Cause Code Backlog (1 month)

Number of CRs Coded w ith Adverse Trend (1 month) 10 Engineering M arch 2013 Engineering M arch 2014 47 7

9 0

9 7

8 0

151 83 252 380 241 68 15 15 965 1,148 212 733 1,930 2,294 261 124 26 15 1,785 1,270 465 144 774 956 320 321 917 497 Timeliness Overdue Priorities (1 month)

Number of Overdue Non-ACA and Non-RCA REs (1 month)

Number of Overdue Corrective Actions (3 month total)

Average Time to Perform RCAs (12 month avg.)

Number of Overdue Simple Causes (1 month)

Average Time to Perform Tier 2 ACAs (1 month)

Average Time to Perform Tier 1 ACAs (1 month avg.)

Median Age of Open Non-Outage AIs (days) (1 month)

Average Time to Perform Simple Causes (1 month)

Oldest Open Non-Outage AI (days) (1 month)

Number of Open Non-Outage AIs > 365 days (1 month)

Number of Open CA's (1 month)

Number of Open CAPR's (1 month)

Number of Open Outage-Related AIs (1 month)

Engineering CAP Health: March 2013 - March 2014 Comparison CRs in Ready to Close (1 month)

Number of Open RA's > 365 days (1 month)

Median Age of Open RA's (days) (1 month)

Number of Open RE's (1 month) 11 12 0

500 1000 1500 2000 2500 3000 3500 4000 Number of Action items Dec13 Jan14 Feb14 Mar14 Apr14 Number of AC Actions 3,683 3,459 3,230 2,652 2,374 Closure Rate for Engineering of Active Action items A, B, C

13

  • Observations and trends for:

- Corrective Action Products

- Quality of Engineering Products

- Operability Evaluations

- Reportability Determinations Engineering Products 14 50.59 Screens Applicability Determinations Applicability Determinations 72.48 Screens Engineering Products Immediate Operability Determinations Operability Evaluations Reportability Evaluations 50.59 Evaluations Total Percent Accepted 2013 82.80%

94.29%

98.53%

90.75%

98.00%

70.30%

80.43%

78.38%

94.87%

Percent Accepted 2014 100.00%

96.55%

96.43%

92.31%

98.49%

66.67%

81.25%

0 97.56%

0.00%

20.00%

40.00%

60.00%

80.00%

100.00%

120.00%

Percent of Accepted EAG Products Engineering Assurance Group Products 2013-2014 Comparison 15 Design and Licensing Basis Control and Use

  • OPPDs post-restart commitment states:

- After restart, OPPD will complete a significant effort to perform a risk-focused reconstitution of the:

Design basis, Licensing basis, and Updated Safety Analysis Report

- As part of this project, OPPD will:

Ensure proper classification of equipment, Convert to a safety-related Q List approach for equipment classification, and Complete a key calculation review

- A pilot program will be completed during 2014 on a selected system to check & adjust the process, scheduling and resource allocation

- Complete the reconstitution project before the end of the 4th quarter, 2018 15 16 Design and Licensing Basis Control and Use

  • Project Activities Completed or In Progress

- January 2014 - Commenced drafting project request for proposal (COMPLETE)

- February 7, 2014 - Issue project request for proposal to vendors (COMPLETE)

- March 28, 2014 - Vendor proposals due (COMPLETE)

- April 30, 2014 - Award project contract (COMPLETE)

- May 5, 2014 - Commence project (COMPLETE)

- January 2014: Commenced review of key calculations Pre-restart 93 calculations were reviewed, with 45 revisions recommended 330 of 382 key calculations have been reviewed with 147 revisions recommended Calculation issues identified to date have been determined to be not consequential, but calculations must be brought up to todays standards 16

17 Design and Licensing Basis Control and Use

  • Project Activities to be Completed

- June 30, 2014 - Complete Phase 1 (Develop project processes/procedures)

- December 31, 2014 - Complete Phase 2 (Pilot program - NRC commitment)

- February 1, 2015 - Complete project status assessment Approximately every six months between Feb. 1, 2015, and Dec. 31, 2018 -

Perform project status assessments

- February 28, 2015 - Complete Phase 3 (Incorporate lessons learned from pilot program)

- December 31, 2018 - Complete Phase 4 (Complete reconstitution project - NRC commitment)

- February 1, 2019 - Complete project final effectiveness review 17 18 Design and Licensing Basis Control and Use

  • Project Oversight

- Oversight to be provided as follows:

  • OPPD project manager who is independent of the production work
  • OPPD/Exelon senior management
  • Periodic project status assessments
  • Independent project oversight board
  • FCS Nuclear Oversight Department
  • Nuclear Safety Review Board 18 19

Evaluate the structural design margin for the containment internal structure, and reactor cavity and compartments, and resolve any deficiencies in accordance with FCSs CAP Regarding Beams 22A and Beam 22B under Safety Injection Tanks 6B/D, resolve any deficiencies in accordance with the CAP Resolve and correct any deficiencies surrounding the reactor vessel head stand (RVHS) prior to its next use Containment Internal Structures 20

  • Resolution strategy for 2015 refueling outage

- Install columns in the basement of the containment building under floor Beams 22A and Beam 22B to reduce the loading on the two floor beams

- Replace the existing RVHS pedestal supports with a structural steel box frame that spans the floor and transfers the loads to adjacent walls and columns

- Preliminary design will be complete by third quarter 2014 Containment Internal Structures

21 Site Operational Focus Procedures

  • Procedure focus

- Quality

- Use and Adherence

- Level of Detail

  • Cornerstone for performance

- Emergency and Abnormal Operations Demonstrated using simulator Upgrades continue

- Normal Operations Support plant operations Require verbatim compliance

- Administrative Station-wide effort 22 Integration status

  • More than 4,000 tasks completed

- Design Review Board

- Human Performance Fundamentals

- Nuclear Oversight Processes

- Learning Programs

- Operations Standards and Expectations

  • Approximately 8,000 tasks remain, with 6,000 of these scheduled for completion in 2014

- Weekly integration status meetings to review schedule adherence

  • Lessons Learned

- Data Sharing

- Gap Analysis The Exelon Nuclear Management Model 23 Nuclear Oversight Independent Assessment Plant Observations and Performance 24 Five Flooding Recovery Post-Restart Action commitments outlined in Section 2 of the Confirmatory Action Letter (CAL)

Three of the Section 2 Flooding Recovery Post-Restart Action commitments have been submitted to the NRC resident inspectors Item 4.4.3.1 - Gather flood response lessons learned through condition report reviews to determine if procedure or strategy changes should be implemented (completed December 12, 2012)

Item 4.4.3.3 - Implement procedure and strategy changes as indicated by the lessons learned review conducted (completed February 20, 2013)

Item 1.2.3.21 - Inspect tank and equipment on demineralized water tank for damage (completed February 10, 2014)

Two of the Section 2 Flooding Recovery Post-Restart Action commitments are scheduled Item 4.4.3.2 - Review flood design basis and determine if the 2011 flood event provides additional information that should drive design basis changes Item 1.2.3.82 - Perform independent spent fuel storage installation route load test Flooding Recovery Action Plans

25

  • Project scope Flooding reevaluation and seismic evaluation Flooding and seismic walkdowns

Results submitted to the NRC

Actions ongoing Mitigating strategies for beyond design basis external events Strategy developed and submitted to NRC

Portable equipment pre-staged at FCS

Procedures (Admin/Operations/PM/Testing)

Staffing

Communications (internal and external)

Spent Fuel Pool Instrumentation (SFPI)

SFPI modifications submitted to the NRC Fukushima Response Project Portable Submersible Pumps 26

  • Plant Status
  • Problem Identification and Resolution
  • Engineering Products
  • Design and Licensing Basis Control and Use
  • Containment Internal Structures
  • Site Operational Focus
  • Integration
  • Nuclear Oversight
  • Closing Remarks Closing Remarks