August 8, 2013 SUMMARY OF JULY 24, 2013 MEETING WITH OMAHA PUBLIC POWER DISTRICT

Transcription

1 UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I V 1600 EAST LAMAR BLVD ARLINGTON, TEXAS August 8, 2013 LICENSEE: FACILITY: SUBJECT: Omaha Public Power District (OPPD) Fort Calhoun Station SUMMARY OF JULY 24, 2013 MEETING WITH OMAHA PUBLIC POWER DISTRICT On July 24, 2013, a Category 1 meeting was held between the U.S. Nuclear Regulatory Commission (NRC) and Omaha Public Power District (OPPD) at the Ramada Plaza Omaha Hotel and Convention Center located at 3321 South 72nd Street, Omaha, Nebraska. The NRC presented the status of Inspection Manual Chapter 350 inspection to review the licensee s progress in addressing items on the Confirmatory Action Letter Restart Checklist (Enclosure 1.) The licensee presented details of their progress for issue resolution and plant restart activities (Enclosure 2.) A video of the public meeting will be posted on the website devoted to the special oversight at Fort Calhoun Station, available at: In accordance with 10 CFR of the NRC s Rules of Practice, a copy of this letter and its enclosures will be available electronically for public inspection in the NRC s Public Document Room or from the Publicly Available Records (PARS) component of the NRC s Agency wide Documents Access and Management System (ADAMS). ADAMS is accessible from the Public Electronic Reading Room page of the NRC s public web site at: To receive a summary of future meetings and other plant-specific distributions, you must subscribe to the Operating Reactor Correspondence electronic distribution for this plant via: Once subscribed, if you wish to discontinue receiving electronic distribution, you may unsubscribe at any time by visiting the same web address above. CONTACT: Michael Hay, RIV/DRP (817) Docket No.: Enclosure 1: NRC Presentation Slides Enclosure 2: OPPD Presentation Slides

2 Fort Calhoun Station Public Meeting Nuclear Regulatory Commission July 24, 2013 Omaha, Nebraska

3 Opening and Introductions Welcome Introduction of NRC personnel

4 Purpose NRC will discuss current status of assessment activities associated with the Confirmatory Action Letter Restart Checklist OPPD will discuss activities to support plant restart Public comments and question

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6 NRC PERSPECTIVES NRC Inspections Independent Thorough Focused on Safety

7 NRC PERSPECTIVES Fort Calhoun Station is making progress People Plant Processes

8 STATUS OF RESTART CHECKLIST Majority of Restart Checklist Items have been inspected A number of areas have been adequately addressed A number of areas require additional inspection

9 Item Number Description of Item 1 Causes of Significant Performance Deficiencies and Assessment of Organizational Effectiveness Current Status 1.a Flooding Issue Yellow Finding Open Corrective actions adequate, Extent of Condition under review 1.b Reactor Protection System contact failure White Finding 1.c Electrical bus modification and maintenance Red Finding Open Corrective actions adequate, Causes under review Open Corrective actions adequate, Extent of condition under review

10 Item Number Description of Item 1.d Security Greater than Green Findings Closed 1.e Third-Party Safety Culture Assessment Closed 1.f Integrated Organizational Effectiveness Assessment 1.g Safety System Functional Failures White Performance Indicator 2 Flood Restoration and Adequacy of Structures, Systems, and Components 2.a Flood Recovery Plan actions associated with facility and system restoration 2.b System readiness for restart following extended plant shutdown Current Status Closed Open Inspections in progress Open Majority of items inspected and closed Open Inspections in progress

11 Item Number Description of Item 2.c Qualification of containment electrical penetrations Current Status Open Inspections in progress 2.d Containment internal structure Open Inspections in progress 3 Adequacy of Significant Programs and Processes 3.a Corrective Action Program Open Inspected, Long term corrective actions under review 3.b Equipment design qualifications Open Inspections in progress

12 Item Number Description of Item Current Status 3.c Design changes and modifications Open Inspections in progress 3.d Maintenance Programs Open Inspections in progress 3.e Operability Process Open Inspected, Long term corrective actions under review 3.f Quality Assurance Closed 4 Review of Integrated Performance Improvement Plan Under review

13 Item Number Description of Item 5 Assessment of NRC Inspection Procedure Key Attributes Current Status 5.a Design Open Inspection in progress, Long term corrective actions under review 5.b Human Performance Closed 5.c Procedure Quality Open Inspected, Corrective actions under review 5.d Equipment Performance Open Inspections in progress 5.e Configuration control Open Inspections in progress

14 Item Number Description of Item 5.f Emergency response Closed 5.g Occupational radiation safety Closed 5.h Public radiation safety Closed 5.i Security Closed Current Status

15 OPPD Discussion Lou Cortopassi Vice President and Chief Nuclear Officer Omaha Public Power District

16 NRC Remarks Closing Remarks

17 Open discussion

18 Contacting the NRC Report an emergency (301) (call collect) Report a safety concern (800) Allegation@nrc.gov General information or questions

19 Fort Calhoun Station Driving Through Restart Public Meeting with the U.S. Nuclear Regulatory Commission 1 July 24, 2013

20 Topics for Discussion Recovery Actions Completed People, Processes and Plant Progress Toward Restart Post-Restart Plan for Sustained Improvement Independent Assessment Closing Remarks 2

21 3 Progress Toward Restart Overarching causes of performance decline addressed for restart Organizational Effectiveness Leadership, accountability, governance and oversight Safety Culture Leadership values and Safety Conscious Work Environment Problem Identification and Resolution Corrective Action Program (CAP) effectiveness and bias for action Design and licensing basis control

22 Progress Toward Restart People Improved safety and human performance Ready for Restart Developed and implemented a safety and human performance strategy with accountability-driven expectations» Rigorous work planning» Discipline in completing work» Required procedure adherence» Supervisors and managers in the field monitoring work performance 4

23 Progress Toward Restart People Established Human Performance Oversight Committee» Senior managers and department staff» Review department performance weekly» Maintain focus on human performance strategies 5 Performance monitoring Training Communications Fort Calhoun industrial safety and human error rates are 1 st quartile of U.S. nuclear power plants

24 Progress Toward Restart People Strengthened operational focus throughout the organization Ready for Restart Incorporated industry-best practices into FCS operational decision-making procedure Trained operators and monitoring their behaviors in» Using risk assessment tools» Anticipating system response during evolutions 6

25 Progress Toward Restart People Established and monitoring operational decision-making expected behaviors All departments aligned in supporting Shift Manager for safe operations» Outage Control Center 24/7 safely controlling outage work» Senior leadership providing direct oversight of operational safety focus 7

26 Progress Toward Restart Processes Corrective Action Program (CAP) Enhanced procedures, staffing and training Improved station and department corrective action review boards Implemented detailed Exelon Nuclear performance monitoring tools Marked improvement in problem identification, root and apparent cause quality, and timely action closure in targeted work groups Ready for Restart 8

27 Progress Toward Restart Plant Systems evaluated for restart readiness System health readiness reviews of all important systems» Interdisciplinary team of engineering, maintenance and operations staff» Focused on System performance, health and maintenance Risk significant components» Identified necessary actions to be completed before restart 9

28 Progress Toward Restart Plant Containment Internal Structures (CIS) Fuel reload» CIS analysis completed for fuel reload structures remain operable Plant heat-up» Analysis of reactor cavity and compartments and CIS being finalized for heat-up 10

29 Progress Toward Restart Plant Containment penetrations replaced All new penetrations installed Teflon material susceptible to radiation degradation eliminated from containment integrity boundary All post-modification testing scheduled to be completed for heat-up 11

30 Progress Toward Restart Processes Electrical equipment environmental qualification program Re-evaluated high energy line break analyses to develop harsh environment profiles Analyzed equipment in harsh environments Initiated modifications to restore environmental qualification of electrical equipment Actions being completed for heat-up include:» Final field verifications and actions scheduled to be completed before heat-up» Complete final documentation of results 12

31 Progress Toward Restart Processes Equipment Service Life Identified and performed necessary preventative maintenance tasks for safety-significant components Identified and implemented part replacement activities where necessary All work completed for components necessary for fuel reload Established a dedicated Project Manager to focus on project completion prior to heat-up All remaining work items scheduled to be completed before heat-up 60% of post restart reviews completed 13

32 Progress Toward Restart Plant Tornado missile engineering analysis and barrier installation completed for fuel reload 14 separate changes for tornado missile barriers installed in the plant Engineering analysis and engineering changes in progress for plant heat-up 14

33 Progress Toward Restart Plant Significant safety enhancement regarding tornado missile protection Aligned with current NRC requirements» 4,000 pound automobile at 135 feet per second» 287 pound 15 foot 6 inch pipe at 135 feet per second» 1 inch diameter solid sphere at 26 feet per second 15

34 Progress Toward Restart Processes Design and licensing basis control and use Actions completed before restart» Developed key calculation review program for accuracy and consistency Completed Phase 1, Phase 2 in progress» Performed structural walk downs of safety-related systems to ensure consistency with design drawings» Trained engineers and operators in utilizing the design and licensing basis for operability determinations and safety screenings/evaluations» Monitoring engineer and operator work product quality utilizing review comments and scores from independent Engineering Assurance Group 16

35 Progress Toward Restart Processes Design and licensing basis control and use Actions to be completed after restart» Define model for form and content of design basis and licensing basis documents» Reconstitute design and licensing basis in a desktop available platform» Perform annual risk-significant system design reviews until completion of reconstitution» Train station staff on utilizing new design and licensing basis resources» Maintain Engineering Assurance Group while necessary to provide independent oversight of engineering work quality 17

36 Developed new flooding mitigation system that is beyond regulatory requirements Completed reactor analysis to support system design Procured equipment and constructed and tested portable system» Electrical generator with fuel supply» Appropriate pumping systems» Necessary piping, hoses and connections / fittings Revised abnormal operating procedures procedures validated on simulator and during field walk downs Established equipment storage location Finalizing emergency preparedness and security procedures Developing preventative maintenance and testing procedures 18 Progress Toward Restart Plant

37 Preparing to Reload Fuel Fuel reload milestones Equipment tested, surveillances completed Personnel trained and qualified to job assignments Reactor Engineers developed reactor core reloading plan Submitted license amendment request to implement current NRC tornado protection standards 19

38 Implementing Consolidated Operational Plan Systems run and readiness verified Safety Systems Inventory make-up Boration flowpath Emergency Diesel Generators Radiation Monitors Primary systems Nuclear Instrumentation System Shutdown Cooling System Cooling systems Raw Water System Component Cooling System Spent Fuel Pool Cooling System Secondary systems Circulating Water System Condensate System 20 Preparing Plant for Heat-up

39 Implementing Consolidated Operational Plan Integrated organizational performance 21 Preparing Plant for Heat-up Operations Engineering Maintenance Chemistry Radiation Protection Security Training Senior management oversight and monitoring Independent oversight

40 Implementing Consolidated Operational Plan Operations department readiness 22 Preparing Plant for Heat-up Benchmarked operating plants and frequent external assessments of plant operations Fast Cruise just-in-time training Shift mentoring during heat-up Monitoring system operation Critical Parameter Trending System Temperature, Pressures, Flows Equipment Monitoring Bearing temperatures Vibration Thermography

41 Progress Toward Restart Plant Equipment Reliability Enhancements Containment electrical penetrations replaced Emergency diesel generator voltage regulators replaced Equipment Service Life addressed (hundreds of component/part replacements) 4160 Volt breakers replaced and maintained Reactor Protection System power supplies replaced Chemical and Volume Control System piping replaced with additional supports Raw water pumps/motors overhauled Manholes 5 and 31 restored Auxiliary feedwater pump motor refurbished Various parts and components replaced to address environmental qualification Extended Power Uprate modifications Main generator stator replacement Isophase bus duct cooling enhancement Nuclear detector well coolers modification Supports for several systems modified Heater drain tank modified Digital turbine controls installed Main generator stator replacement 23

42 Preparing the Organization and Plant for Heat-up Procedure Upgrade Project Alarm Response Procedures (ARP) Abnormal Operating Procedures (AOP) Emergency Operating Procedures (EOP) Incorporated Industry Best Practices Added detail, clarified actions, enhanced technical detail Revisions in progress including Cross disciplinary reviews Field verification and validation of actions Confirming procedure flow Corrections and enhancements cover extent of condition 24

43 Post-Restart Plan for Sustained Improvement OPPD has completed early implementation of the proven Exelon Nuclear Management Model (ENMM) performance improvement Policy and Program, and the procedure for the Performance Improvement Integrated Matrix (PIIM) 25

44 Post-Restart Plan for Sustained Improvement Plan for Sustained Improvement (PSI) using the PIIM has been developed and is in final review 78 detailed corporate, site and department level action plans included in the PIIM Key Drivers for Achieving and Sustaining Excellence highlighted in the PSI 26

45 Key Drivers address multiple areas including Organizational effectiveness, safety culture, and safety conscious work environment Problem identification and resolution Performance improvement and learning programs Design and licensing basis control and use Site operational focus Procedures Equipment performance Programs Nuclear oversight Transition to the ENMM and integration into the Exelon Nuclear Fleet 27 Post-Restart Plan for Sustained Improvement

46 28 Independent Assessments

47 Progress Toward Restart Processes Actions taken to improve independent oversight Established OPPD policy and corporate nuclear safety oversight committee Established Nuclear Oversight Department implemented Exelon Nuclear model» New experienced leader» Focus on behaviors that result in excellence Strengthened Employee Concerns Program Implemented Exelon Nuclear Safety Review Board at Fort Calhoun Results Expectations clear Assessments intrusive Actively engaged Reinforcing expected values and behaviors 29

48 Results of Nuclear Oversight Assessments Areas that require additional management attention CAP implementation with focus on engineering Timely completion of causal analyses Closure quality and timeliness Design and Licensing Basis activities Engineering Assurance Group observations Quality records not maintained properly resulting in rework Areas found acceptable Management meetings and quality challenges Integrated Performance Improvement Plan and Plan for Sustained Improvement after restart 30

49 Progress on Restart Checklist Items Restart Checklist Item Issue Description Scoping Discovery Analysis Implementation 1.a Flooding Issue b Reactor Contactor Failure c Electrical Bus Mod and Maintenance d Security Issue e Safety Culture f Organizational Effectiveness g Safety System Performance Indicator *** *** *** 50 2.a Flood Recovery Restoration Actions b.1 System Health Reviews b.2 Reactor Safety Strategic Performance Area Review b.3 Flood Impact on Soils and Structures b.4 Containment Penetration Design b.5 Containment Internal Structure Design

50 Progress on Restart Checklist Items Restart Checklist Item Issue Description Scoping Discovery Analysis Implementation 3.a Corrective Action Program a.1 Identification, Analysis and Correction of Performance Deficiencies b.1 Safety Related Parts b.2 Equipment Qualification c.1 Vendor Modifications c.2 10CFR50.59 Screening and Safety Evaluations d.1 Vendor Manuals d.2 Equipment Service Life e.1 Operability Determinations e.2 Degraded / Non-Conforming Equipment f Quality Assurance

51 Closing Remarks Tonight, we updated you on Recovery Actions Completed People, Processes and Plant Progress Toward Restart Post-Restart Plan for Sustained Improvement Independent Assessment 33