ML13220A779

Summary of July 24, 2013 Meeting with Omaha Public Power District

ML13220A779
Person / Time
Site:	Fort Calhoun
Issue date:	08/08/2013
From:	NRC Region 4
To:	Omaha Public Power District
Hay M
References
Download: ML13220A779 (51)

Text

August 8, 2013 LICENSEE: Omaha Public Power District (OPPD)

FACILITY: 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:

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

-oversight.html

. In accordance with 10 CFR 2.390 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:

http://www.nrc.gov/readingrm/adams.html

. To receive a summary of future meetings and other plant

-specific e

-mail distributions, you must subscribe to the Operating Reactor Correspondence electronic distribution for this plant via:

http://www.nrc.gov/public

-involve/listserver/plants

-by-region.html 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) 200-1147 Docket No.:

50-285 Enclosure 1:

NRC Presentation Slides Enclosure 2:

OPPD Presentation Slides U N I T E D S T A T E S N U C L E A R R E G U L A T O R Y C O M M I S S I O N R E G I O N I V1600 EAST LAMAR BLVD A R L I N G T O N , T E X A S 7 6 0 1 1-4511 Fort Calhoun Station Public Meeting Nuclear Regulatory Commission July 24, 2013 Omaha, Nebraska Opening and Introductions Welcome Introduction of NRC personnel 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

NRC PERSPECTIVES NRC Inspections Independent Thorough Focused on Safety NRC PERSPECTIVES Fort Calhoun Station is making progress People Plant Processes 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 Item Number Description of Item Current Status 1 Causes of Significant Performance Deficiencies and Assessment of Organizational Effectiveness 1.a Flooding Issue Yellow Finding Open Corrective actions adequate, Extent of Condition under review 1.b Reactor Protection System contact failure White Finding Open Corrective actions adequate, Causes under review 1.c Electrical bus modification and maintenance Red Finding Open Corrective actions adequate, Extent of condition under review Item Number Description of Item Current Status 1.d Security Greater than Green Findings Closed 1.e Third-Party Safety Culture Assessment Closed 1.f Integrated Organizational Effectiveness Assessment Closed 1.g Safety System Functional Failures White Performance Indicator Open Inspections in progress 2 Flood Restoration and Adequacy of Structures, Systems, and Components 2.a Flood Recovery Plan actions associated with facility and system restoration Open Majority of items inspected and closed 2.b System readiness for restart following extended plant shutdown Open Inspections in progress Item Number Description of Item Current Status 2.c Qualification of containment electrical penetrations 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 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 Item Number Description of Item Current Status 5 Assessment of NRC Inspection Procedure 95003 Key Attributes 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 Item Number Description of Item Current Status 5.f Emergency response Closed 5.g Occupational radiation safety Closed 5.h Public radiation safety Closed 5.i Security Closed OPPD Discussion Lou Cortopassi Vice President and Chief Nuclear Officer Omaha Public Power District NRC Remarks Closing Remarks Open discussion Contacting the NRC Report an emergency (301) 816-5100 (call collect) Report a safety concern (800) 695-7403 Allegation@nrc.gov General information or questions www.nrc.gov 1 Fort Calhoun Station Driving Through Restart Public Meeting with the U.S. Nuclear Regulatory Commission July 24, 2013 2 Recovery Actions Completed People, Processes and Plant Progress Toward Restart Post-Restart Plan for Sustained Improvement Independent Assessment Closing Remarks Topics for Discussion 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 4 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 Progress Toward Restart People 5 Established Human Performance Oversight Committee >>Senior managers and department staff >>Review department performance weekly >>Maintain focus on human performance strategies Performance monitoring Training Communications Fort Calhoun industrial safety and human error rates are 1st quartile of U.S. nuclear power plants Progress Toward Restart People 6 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 Progress Toward Restart People 7 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 Progress Toward Restart People 8 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 Progress Toward Restart Processes 9 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 Progress Toward Restart Plant 10 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 Progress Toward Restart Plant 11 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 Progress Toward Restart Plant 12 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 Progress Toward Restart Processes 13 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 Progress Toward Restart Processes 14 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 Progress Toward Restart Plant 15 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 Progress Toward Restart Plant 16 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 Progress Toward Restart Processes 17 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 Progress Toward Restart Processes 18 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 Progress Toward Restart Plant 19 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 Preparing to Reload Fuel 20 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 Preparing Plant for Heat-up 21 Implementing Consolidated Operational Plan Integrated organizational performance Operations Engineering Maintenance Chemistry Radiation Protection Security Training Senior management oversight and monitoring Independent oversight Preparing Plant for Heat-up 22 Implementing Consolidated Operational Plan Operations department readiness Benchmarked operating plants and frequent external assessments of plant operations -in-time training Shift mentoring during heat-up Monitoring system operation Critical Parameter Trending System Temperature, Pressures, Flows Equipment Monitoring Bearing temperatures Vibration Thermography Preparing Plant for Heat-up 23 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 Progress Toward Restart Plant Equipment Reliability Enhancements 24 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 Preparing the Organization and Plant for Heat-up 25 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) Post-Restart Plan for Sustained Improvement 26 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 Post-Restart Plan for Sustained Improvement 27 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 Post-Restart Plan for Sustained Improvement 28 Independent Assessments 29 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 Progress Toward Restart Processes 30 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 Results of Nuclear Oversight Assessments 31 Restart Checklist Item Issue Description Scoping Discovery Analysis Implementation 1.a Flooding Issue 100 100 100 72 1.b Reactor Contactor Failure 100 100 100 95 1.c Electrical Bus Mod and Maintenance 100 100 100 88 1.d Security Issue 100 100 100 100 1.e Safety Culture 100 100 100 100 1.f Organizational Effectiveness 100 100 100 100 1.g Safety System Performance Indicator *** *** *** 50 2.a Flood Recovery Restoration Actions 100 100 100 94 2.b.1 System Health Reviews 100 100 100 96 2.b.2 Reactor Safety Strategic Performance Area Review 100 100 100 100 2.b.3 Flood Impact on Soils and Structures 100 100 100 100 2.b.4 Containment Penetration Design 100 100 100 85 2.b.5 Containment Internal Structure Design 100 100 95 85 Progress on Restart Checklist Items 32 Restart Checklist Item Issue Description Scoping Discovery Analysis Implementation 3.a Corrective Action Program 100 100 100 95 3.a.1 Identification, Analysis and Correction of Performance Deficiencies 100 100 100 100 3.b.1 Safety Related Parts 100 100 100 80 3.b.2 Equipment Qualification 100 100 95 75 3.c.1 Vendor Modifications 100 100 100 70 3.c.2 10CFR50.59 Screening and Safety Evaluations 100 100 100 95 3.d.1 Vendor Manuals 100 100 100 100 3.d.2 Equipment Service Life 100 100 100 75 3.e.1 Operability Determinations 100 100 100 95 3.e.2 Degraded / Non-Conforming Equipment 100 100 100 95 3.f Quality Assurance 100 100 100 100 Progress on Restart Checklist Items 33 Tonight, we updated you on Recovery Actions Completed People, Processes and Plant Progress Toward Restart Post-Restart Plan for Sustained Improvement Independent Assessment Closing Remarks