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| number = ML12338A191 | | number = ML12338A191 | ||
| issue date = 12/03/2012 | | issue date = 12/03/2012 | ||
| title = | | title = Meeting Summary with Omaha Public Power District to Discuss Update of Issues and Oversight Activities at Fort Calhoun Station | ||
| author name = Hay M | | author name = Hay M | ||
| author affiliation = NRC/RGN-IV/DRP | | author affiliation = NRC/RGN-IV/DRP | ||
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| page count = 17 | | page count = 17 | ||
}} | }} | ||
=Text= | |||
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I V 1600 EAST LAMAR BLVD ARLINGTON, TEXAS 76011-4511 December 3, 2012 LICENSEE: Omaha Public Power District (OPPD) | |||
FACILITY: Fort Calhoun Station | |||
==SUBJECT:== | |||
==SUMMARY== | |||
OF NOVEMBER 15, 2012, MEETING WITH OMAHA PUBLIC POWER DISTRICT On November 15, 2012, a Category 1 meeting was held between the U.S. Nuclear Regulatory Commission (NRC) and Omaha Public Power District (OPPD) at The Dana College Gardner-Hawks Center (gymnasium), 2848 College Drive, Blair, Nebraska. | |||
The NRC presented an update of issues and oversight activities at Fort Calhoun Station. | |||
Additionally, the NRC provided details regarding the Restart Checklist Basis document. A copy of the presentation is enclosed (Enclosure 1). OPPD presented details of plant status, ongoing work and restart commitments, and independent oversight activities (Enclosure 2). | |||
A video of the public meeting, and responses to the questions directed to the NRC, 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 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/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 : NRC Presentation slides : OPPD Presentation slides | |||
Omaha Public Power District Electronic Distribution by RIV: | |||
RIV Regional Administrator (Elmo.Collins@nrc.gov) | |||
RIV Acting Deputy Regional Administrator (Steven.Reynolds@nrc.gov) | |||
RIV DRP Director (Kriss.Kennedy@nrc.gov) | |||
RIV Acting DRP Deputy Director (Barry.Westreich@nrc.gov) | |||
RIV Acting DRS Director (Tom.Blount@nrc.gov) | |||
RIV Acting DRS Deputy Director (Jeff.Clark@nrc.gov) | |||
RIV Senior Resident Inspector (John.Kirkland@nrc.gov) | |||
RIV Resident Inspector (Jacob.Wingebach@nrc.gov) | |||
RIV Branch Chief, DRP/F (Michael.Hay@nrc.gov) | |||
RIV Senior Project Engineer, DRP/F (Rick.Deese@nrc.gov) | |||
RIV Project Engineer, DRP/F (Chris.Smith@nrc.gov) | |||
RIV Project Engineer, DRP/F (Jesse.Rollins@nrc.gov) | |||
RIV Public Affairs Officer (Victor.Dricks@nrc.gov) | |||
RIV Public Affairs Officer (Lara.Uselding@nrc.gov) | |||
RIV Project Manager (Lynnea.Wilkins@nrc.gov) | |||
RIV Branch Chief, DRS/TSB (Ray.Kellar@nrc.gov) | |||
RIV RITS Coordinator (Marisa.Herrera@nrc.gov) | |||
RIV Regional Counsel (Karla.Fuller@nrc.gov) | |||
Congressional Affairs Officer (Jenny.Weil@nrc.gov) | |||
OEMail Resource OEWEB Resource (Sue.Bogle@nrc.gov) | |||
RIV/ETA: OEDO (Cayetano.Santos@nrc.gov) | |||
RIV RSLO (Bill.Maier@nrc.gov) | |||
MC 0350 Panel Chairman (Anton.Vegel@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) | |||
ADAMS: No Yes SUNSI Review Complete Reviewer Initials: CS Publicly Available Non-Sensitive Category A. Non-publicly Available Sensitive KEYWORD: 0350 FCS RIV:BC:DRP/F PAO SLO D:DRP MHay VDricks WMaier KKennedy | |||
/RA/ /RA/ /RA/ /RA/ | |||
11/28/12 11/29/12 11/30/12 11/30/12 OFFICIAL RECORD COPY T=Telephone E=E-mail F=Fax | |||
Opening and Introductions Fort Calhoun Station Public Meeting | |||
* Welcome Nuclear Regulatory Commission | |||
* Introduction of NRC personnel November 15, 2012 Blair, Nebraska Purpose | |||
* Status of NRC and OPPD actions | |||
- NRC will present status of inspections and issuance of basis document | |||
- OPPD will present details of plant flood recovery actions | |||
* Allow for public interaction and questions Enclosure 1 | |||
NRC Inspections Basis Document | |||
* Overview of Basis Document | |||
* Ongoing Inspections - Follows CAL Restart Checklist Structure | |||
- Permanent local-based resident - Provides Detailed Scope p of Inspection p Items inspectors - Living Document | |||
- Inspections by other NRC Specialists - Available for Public Review | |||
* http://www.nrc.gov/info-finder/reactor/fcs/special-oversight.html | |||
* Future Inspections RESTART CHECKLIST Basis Document Item Number Description Closure Date Causes of Significant Performance Deficiencies and 1 Assessment of Organizational Effectiveness 1.a Flooding Issue - Yellow finding 1.b Reactor Protection System contact failure - White finding 1.c Electrical bus modification and maintenance - Red finding 1.d Security - Greater than green findings 1.e Third-Party Safety Culture Assessment 1.f Integrated Organizational Effectiveness Flood Restoration and Adequacy of Structures, Systems, 2 and Components Flood Recovery Plan actions associated with facility and 2.a system restoration 2.b System readiness from extended shutdown Enclosure 1 | |||
Basis Document Basis Document Basis Document Current Status | |||
* Comprehensive and Detailed Inspection Strategy Developed | |||
* Performing P f i F Focusedd IInspections ti | |||
- Flood and Fire Recovery Actions | |||
- Performance Improvement Activities | |||
- Containment Penetrations and Internal Structure Issues Enclosure 1 | |||
Current Status Path Forward | |||
* Currently No Restart Checklist Items are Fully Completed by the Licensee and Ready for Final NRC Review PERFORM THOROUGH and INDEPENDENT VERIFICATION of PLANT SAFETY OPPD Presentation NRC Remarks Lou Cortopassi Site Vice Vice-President President / Chief Nuclear Officer Omaha Public Power District Closing Remarks Enclosure 1 | |||
Open to the public | |||
* The NRC places a high priority on keeping the public and stakeholders informed of its activities | |||
* At www.nrc.gov, you can: | |||
- Find p public meeting g dates and transcripts; p | |||
Open discussion - Read NRC testimony, speeches, press releases, and policy decisions; | |||
- Access the agencys Electronic Reading Room to find NRC publications and documents; and | |||
- Subscribe to automatically receive correspondence from the NRC Contacting the NRC | |||
* Report an emergency | |||
- (301) 816-5100 (call collect) | |||
* Report a safety concern | |||
- (800) 695 695-7403 7403 | |||
- Allegation@nrc.gov | |||
* General information or questions | |||
- www.nrc.gov Enclosure 1 | |||
Topics for Discussion Driving Through Restart | |||
* Plant Status - Fixing the Public Meeting with the U.S. Nuclear Regulatory Plant Commission | |||
* Progress on Commitments for Restart | |||
* Restart Decision-Making | |||
* Plan for Sustained Improvement | |||
* Independent Assessment | |||
* Closing Remarks November 15, 2012 1 2 Plant Status Industrial Safety Overview InjuryComparisonSummary | |||
* Safety Performance 2011 2012 | |||
* Human Performance UntreatedInjuries: 23 18 | |||
* Fixing the Plant FirstAidInjuries: 22 5 OSHARecordable: 21 1 LostTime/Restricted: 1 0 2012dataJanuary1st toNovember14th 3 4 Enclosure 2 | |||
HumanPerformanceGoals Human Performance Overview DepartmentLevelPerformanceIssues WhatDoes"Excellence"LookLike? | |||
HumanPerformanceSummary 140 134 2011 2012 120 Stationlevelissues 9 1 100 80 Departmentlevelissues 134 45 **Department Level Performance Goal 60 52 *2012 data January 1st to November 7th 40 25 45 12 20 6 6 ToDate* | |||
2012dataJanuary1st toNovember14th 0 2011 **2012 **2013 **2014 **2015 **2016 IndustryBestisintheRangeof6to12peryear 5 6 Fixing the Plant Fixing the Plant Emergency Diesel 480 Volt AC Train A Generator No. 1 Bus Maintenance Voltage Regulator Complete Work Complete 7 8 Enclosure 2 | |||
ContinuedProgress OPPDCommitmentsforRestart | |||
* Station Priorities 1. Identify causes and implement corrective actions for safety significant findings (Checklist 1.a through 1.d) | |||
Safety 2. Assess safety culture and organizational effectiveness | |||
Human Performance and implement improvement actions (Checklist 1.e and 1.f) | |||
Insert Picture Fix the Plant 3. Assess and resolve flooding impact, evaluate systems, | |||
Corrective Action and ensure plant is ready for restart (Checklist 2.a and 2.b) | |||
Program 4. Assess and improve programs and processes that caused significant performance decline (Checklist 3.a | |||
* Human Behavior through 3.f) | |||
Continues to Improve 5. Implement the Integrated Performance Improvement Plan (Checklist 4) | |||
* We are Fixing the Plant 6. Submit Fort Calhoun Station Restart Report | |||
* Remaining Work is Known 9 10 CAL Commitment No. 1 Commitment 1 1.a. Flooding Issue Progress on Addressing Safety Findings | |||
* Completed Scoping, Discovery and Analysis | |||
* Completed Root Cause Analyses ScopingDiscoveryAnalysisImplementation | |||
* Key Corrective Actions Completed 1.a. Flooding 100% 100% 100% | |||
75% - Replacement of Certain Flood Barriers 1.b. Reactor Prot. - Inspection of All Conduit/Piping Seals Sys. Contactor 100% 100% 75% 75% - Improved Flood Procedures Failure 1.c. Electrical Bus 100% 100% 100% 75% | |||
Modification & 85% | |||
Maintenance Before After 1.d. Security Issue 100% 100% 90% 75% | |||
11 12 Enclosure 2 | |||
CAL Commitment No. 1 CAL Commitment No. 2 1.a. Flooding Issue - Contd Commitment 2 Progress on Safety Culture and Organizational | |||
* Completing Remaining Corrective Actions Effectiveness ScopingDiscoveryAnalysisImplementation | |||
- Intake Cell Level Control Modification 1.e. Safety Culture 100% 100% 100% 93% | |||
- Fire Barrier Certification for Flood Resistance 1.f. Organizational | |||
* Phase A: Confirmed Static Pressure Effectiveness 100% 100% 100% 89% | |||
Resistance | |||
* Phase B: 30-Day Leakage Test Ongoing | |||
* Restart Checklist Closure Package Ready for Inspection - November 30 13 14 CAL Commitment No. 2 CAL Commitment No. 2 1.e. Safety Culture 1.e. Safety Culture - Contd Improvement Actions | |||
* Independent and Internal Assessments Identified Areas for Improvement | |||
* Developed, Communicated and Aligned on Strategic | |||
- Develop and Communicate Strategic Vision, Plan; Vision, Mission, and Values; and Performance Governance and Oversight - Complete Management and Accountability Process | |||
- Enhance Leadership Behaviors - Ongoing | |||
* Bi-Weekly Employee 2Cs Meetings | |||
- Engage Workforce in Decisions Based on Vision - | |||
* Daily Leaders and Weekly Staff Alignment Meetings Ongoing | |||
* Differing Professional Opinion Process Established | |||
- Improve Corrective Action Program - Ongoing | |||
* Safety Conscious Work Environment Training for | |||
- Encourage Questioning Attitude and Challenging Supervisors Complete and Ongoing for Employees - | |||
of Decisions - Ongoing Complete in December | |||
* Re-Assessment Completed in October | |||
- Improve Accountability - Ongoing 15 16 Enclosure 2 | |||
CAL Commitment No. 2 CAL Commitment No. 2 1.e. Safety Culture - Contd 1.e. Safety Culture - Contd Safety Culture Monitoring Results | |||
* Elements of Safety Culture Metric Safety Conscious Work Environment Index | |||
- Safety Conscious Work Environment Index Improving | |||
- Nuclear Safety Culture Principals Index - Management Takes Concerns Seriously | |||
- Engaged Thinking Organization Index - Culture Conducive to Raising Concerns (INPO SOER 10-02) - Awareness and Willingness to Use ECP | |||
- Employee Engagement Index - Comfortable Escalating Concerns | |||
- INPO Organizational Culture Index Nuclear Safety Culture Principles Index Improving | |||
* Metric Monitored Monthly - Input from Pulse - Supervisors Reinforcing use of Human Surveys Performance Tools | |||
- Staff Encouraged to Bring Problems Forward | |||
- Supervisors Reinforcing use of Operating Experience 17 18 CAL Commitment No. 2 CAL Commitment No. 3 1.e. Safety Culture - Contd Commitment 3 Safety Culture Monitoring Results Progress on Systems Ready for Restart | |||
* Management Focus Areas ScopingDiscoveryAnalysisImplementation 2.a. Flood Recovery 93% | |||
100% 100% 100% 91% | |||
- Managing Distractions Restoration Actions | |||
- Inter-Department Communications 100% | |||
2.b.1. System Health 50% | |||
100% 70% 10% | |||
- Coordinating Issues Between Work Groups Reviews | |||
- Employee Concerns Program Confidentiality 2.b.2. Reactor Safety 50% | |||
Strategic Performance 100% 100% 100% | |||
Area Review 0% | |||
19 20 Enclosure 2 | |||
CAL Commitment No. 3 CAL Commitment No. 3 Commitment 3 2.a. Flood Recovery Restoration Actions Progress on Systems Ready for Restart - Contd | |||
* Fort Calhoun Station Flooding Recovery Plan | |||
- 453 Actions in Six Sections ScopingDiscoveryAnalysisImplementation | |||
* Site Restoration 2.b.3. Flood Impact 100% 100% 95% 80% | |||
* Plant Systems and Equipment on Soils & Structures | |||
* Long Term Equipment Reliability 2.b.4. Containment 100% 100% 75% 10% | |||
* Design and Licensing Basis Penetration Design | |||
* Emergency Planning 2.b.5. Containment | |||
* Security 100% 90% 75% 5% | |||
Internal Structure - Flood Restoration Actions Part of the Integrated Design Performance Improvement Plan 21 22 CAL Commitment No. 3 CAL Commitment No. 3 2.a. Flood Recovery Restoration Actions 2.b.1 System Health Reviews | |||
* Total Flood Recovery Plan | |||
- 453 Actions | |||
* Process Documented in a Station Procedure | |||
* Physical Work Complete | |||
* Evaluating Important Plant Systems | |||
- 410 Actions | |||
* Identify Issues that Could Affect System Health | |||
* Closure Review Board Complete | |||
* Enter Issues into Corrective Action Program | |||
- 343 Actions | |||
* Provide Confidence that Systems are Ready for | |||
* NRC Inspection Plan Restart | |||
- 196 Actions | |||
* NRC Inspection Complete | |||
- 67 Actions 23 24 Enclosure 2 | |||
CAL Commitment No. 3 CAL Commitment No. 3 2.b.3. Flood Impact on Soils & Structures 2.b.4 Containment Penetration Design Final Actions | |||
* Local Expert Geotechnical Firms Analysis Final Fort Calhoun Staff Identified 614 Containment Report Issued on September 18, 2012 Penetrations that Could Degrade under Certain Potential Accident Conditions | |||
* Issuance of Final Safety-Qualified Expert Firms Analysis Final Report Delayed | |||
* Approximately 170 Unused Penetrations will be | |||
* Conclusion - No Negative Effects on Safety-Related Capped Structures | |||
* Approximately Ten Penetrations will be Replaced | |||
* Options are Being Evaluated for Resolution of the | |||
* Restart Checklist Closure Package Ready for Remaining Penetrations Inspection - December 25 26 CAL Commitment No. 3 CAL Commitment No. 4 2.b.5 Containment Internal Structure Design Commitment 4 Fort Calhoun Staff Identified Certain Structural Progress on Programs and Processes Elements Inside the Containment may not Meet Ready for Restart ScopingDiscoveryAnalysisImplementation Design Margins - Containment Shell not Affected 3.a. Corrective 100% 100% 100% 70% | |||
Action Program | |||
* Completed As-Built Verifications and Discovery 3.a.1. Identify, Analyze 50% | |||
100% 100% 100% | |||
nearly Complete & Correct Performance Deficiencies | |||
* Developed Engineering Models for Analysis | |||
* Analyzed Internal Structures using Current 3.b.1. Safety 100% 100% 75% 5% | |||
Licensing Requirements Related Parts | |||
* Evaluating Options for Resolution 3.b.2. Equipment 100% 90% 20% | |||
Qualification 60% | |||
27 28 Enclosure 2 | |||
CAL Commitment No. 4 CAL Commitment No. 4 Commitment 4 Commitment 4 Progress on Programs and Processes Progress on Programs and Processes Ready for Restart - Contd Ready for Restart - Contd ScopingDiscoveryAnalysisImplementation ScopingDiscoveryAnalysisImplementation 3.c.1. Vendor 100% 100% 95% 10% 3.e.1. Operability 100% | |||
Modifications 100% 80% 15% | |||
Determinations 3.c.2. 10CFR50.59 20% | |||
100% 98% 75% 3.e.2. Degraded / | |||
Screening & Safety 15% | |||
Non-Conforming 100% 100% 80% | |||
Evaluations Equipment 55% | |||
3.d.1. Vendor 100% 100% 95% | |||
Manuals 3.f. Quality 100% 100% 100% 83% | |||
Assurance 3.d.2. Equipment 100% 100% 95% 5% | |||
Service Life 29 30 CAL Commitment No. 4 CAL Commitment No. 4 3.a. Corrective Action Program (CAP) 3.a. Corrective Action Program (CAP) | |||
* Corrective Action Program Metric Elements | |||
* Fort Calhoun Staff has been Implementing Improved - Condition Report Generation CAP Process for Six Months - Engagement Ratio | |||
- Good Catches | |||
* Process Implementation Improvement and - Self-Identification Rate Effectiveness Observed | |||
- Repeat Events | |||
- Review Rejection Rate | |||
* Expected Behaviors and Culture Being Reinforced | |||
- Age of Reviews and Actions | |||
- Overdue Reviews and Actions | |||
- Number of Open Condition Reports 31 32 Enclosure 2 | |||
CAL Commitment No. 5 CAL Commitment No. 5 Commitment 5 Restart Decision-Making Criteria Integrated Performance Improvement Plan (IPIP) | |||
* Restart Checklist Items Resolved | |||
* Confirmatory Action Letter Commitments Addressed | |||
* IPIP Revision 4 Docketed November 1 | |||
* Operational Readiness Assessment Completed | |||
* Systems, Programs and Departments Determined to be Ready for Restart | |||
* Addresses Restart Decision-Making Process and Criteria | |||
* Independent Assessments Completed | |||
- Nuclear Oversight Department | |||
- Corporate Governance and Oversight Committee | |||
* Describes Plan for Sustained - Safety Audit and Review Committee Improvement | |||
* Restart Report Submitted to NRC 33 34 CAL Commitment No. 5 Plan for Sustained Improvement | |||
* Operating Services Agreement is the Foundation for Achieving and Sustaining Excellence | |||
* Blended OPPD/Exelon Leadership Team Functioning Effectively IndependentAssessments | |||
* Integration Team of Exelon Experts Providing Site Support and Transition Planning in 22 Functional Areas | |||
* Goal - Implement the Exelon Nuclear Management Model and Full Integration into the Exelon Fleet 35 36 Enclosure 2 | |||
OPPDs Commitment Tonight We Updated You on | |||
* Plant Status - Fixing the Plant | |||
* Progress on Commitments for Restart | |||
* Restart Decision-Making | |||
* Plan for Sustained Improvement | |||
* Independent Assessments 37 Enclosure 2}} |
Latest revision as of 09:54, 6 February 2020
ML12338A191 | |
Person / Time | |
---|---|
Site: | Fort Calhoun |
Issue date: | 12/03/2012 |
From: | Hay M NRC/RGN-IV/DRP |
To: | |
References | |
Download: ML12338A191 (17) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I V 1600 EAST LAMAR BLVD ARLINGTON, TEXAS 76011-4511 December 3, 2012 LICENSEE: Omaha Public Power District (OPPD)
FACILITY: Fort Calhoun Station
SUBJECT:
SUMMARY
OF NOVEMBER 15, 2012, MEETING WITH OMAHA PUBLIC POWER DISTRICT On November 15, 2012, a Category 1 meeting was held between the U.S. Nuclear Regulatory Commission (NRC) and Omaha Public Power District (OPPD) at The Dana College Gardner-Hawks Center (gymnasium), 2848 College Drive, Blair, Nebraska.
The NRC presented an update of issues and oversight activities at Fort Calhoun Station.
Additionally, the NRC provided details regarding the Restart Checklist Basis document. A copy of the presentation is enclosed (Enclosure 1). OPPD presented details of plant status, ongoing work and restart commitments, and independent oversight activities (Enclosure 2).
A video of the public meeting, and responses to the questions directed to the NRC, 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 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/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 : NRC Presentation slides : OPPD Presentation slides
Omaha Public Power District Electronic Distribution by RIV:
RIV Regional Administrator (Elmo.Collins@nrc.gov)
RIV Acting Deputy Regional Administrator (Steven.Reynolds@nrc.gov)
RIV DRP Director (Kriss.Kennedy@nrc.gov)
RIV Acting DRP Deputy Director (Barry.Westreich@nrc.gov)
RIV Acting DRS Director (Tom.Blount@nrc.gov)
RIV Acting DRS Deputy Director (Jeff.Clark@nrc.gov)
RIV Senior Resident Inspector (John.Kirkland@nrc.gov)
RIV Resident Inspector (Jacob.Wingebach@nrc.gov)
RIV Branch Chief, DRP/F (Michael.Hay@nrc.gov)
RIV Senior Project Engineer, DRP/F (Rick.Deese@nrc.gov)
RIV Project Engineer, DRP/F (Chris.Smith@nrc.gov)
RIV Project Engineer, DRP/F (Jesse.Rollins@nrc.gov)
RIV Public Affairs Officer (Victor.Dricks@nrc.gov)
RIV Public Affairs Officer (Lara.Uselding@nrc.gov)
RIV Project Manager (Lynnea.Wilkins@nrc.gov)
RIV Branch Chief, DRS/TSB (Ray.Kellar@nrc.gov)
RIV RITS Coordinator (Marisa.Herrera@nrc.gov)
RIV Regional Counsel (Karla.Fuller@nrc.gov)
Congressional Affairs Officer (Jenny.Weil@nrc.gov)
OEMail Resource OEWEB Resource (Sue.Bogle@nrc.gov)
RIV/ETA: OEDO (Cayetano.Santos@nrc.gov)
RIV RSLO (Bill.Maier@nrc.gov)
MC 0350 Panel Chairman (Anton.Vegel@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)
ADAMS: No Yes SUNSI Review Complete Reviewer Initials: CS Publicly Available Non-Sensitive Category A. Non-publicly Available Sensitive KEYWORD: 0350 FCS RIV:BC:DRP/F PAO SLO D:DRP MHay VDricks WMaier KKennedy
/RA/ /RA/ /RA/ /RA/
11/28/12 11/29/12 11/30/12 11/30/12 OFFICIAL RECORD COPY T=Telephone E=E-mail F=Fax
Opening and Introductions Fort Calhoun Station Public Meeting
- Welcome Nuclear Regulatory Commission
- Introduction of NRC personnel November 15, 2012 Blair, Nebraska Purpose
- Status of NRC and OPPD actions
- NRC will present status of inspections and issuance of basis document
- OPPD will present details of plant flood recovery actions
- Allow for public interaction and questions Enclosure 1
NRC Inspections Basis Document
- Overview of Basis Document
- Ongoing Inspections - Follows CAL Restart Checklist Structure
- Permanent local-based resident - Provides Detailed Scope p of Inspection p Items inspectors - Living Document
- Inspections by other NRC Specialists - Available for Public Review
- Future Inspections RESTART CHECKLIST Basis Document Item Number Description Closure Date Causes of Significant Performance Deficiencies and 1 Assessment of Organizational Effectiveness 1.a Flooding Issue - Yellow finding 1.b Reactor Protection System contact failure - White finding 1.c Electrical bus modification and maintenance - Red finding 1.d Security - Greater than green findings 1.e Third-Party Safety Culture Assessment 1.f Integrated Organizational Effectiveness Flood Restoration and Adequacy of Structures, Systems, 2 and Components Flood Recovery Plan actions associated with facility and 2.a system restoration 2.b System readiness from extended shutdown Enclosure 1
Basis Document Basis Document Basis Document Current Status
- Comprehensive and Detailed Inspection Strategy Developed
- Performing P f i F Focusedd IInspections ti
- Flood and Fire Recovery Actions
- Performance Improvement Activities
- Containment Penetrations and Internal Structure Issues Enclosure 1
Current Status Path Forward
- Currently No Restart Checklist Items are Fully Completed by the Licensee and Ready for Final NRC Review PERFORM THOROUGH and INDEPENDENT VERIFICATION of PLANT SAFETY OPPD Presentation NRC Remarks Lou Cortopassi Site Vice Vice-President President / Chief Nuclear Officer Omaha Public Power District Closing Remarks Enclosure 1
Open to the public
- The NRC places a high priority on keeping the public and stakeholders informed of its activities
- At www.nrc.gov, you can:
- Find p public meeting g dates and transcripts; p
Open discussion - Read NRC testimony, speeches, press releases, and policy decisions;
- Access the agencys Electronic Reading Room to find NRC publications and documents; and
- Subscribe to automatically receive correspondence from the NRC Contacting the NRC
- Report an emergency
- (301) 816-5100 (call collect)
- Report a safety concern
- (800) 695 695-7403 7403
- Allegation@nrc.gov
- General information or questions
- www.nrc.gov Enclosure 1
Topics for Discussion Driving Through Restart
- Plant Status - Fixing the Public Meeting with the U.S. Nuclear Regulatory Plant Commission
- Progress on Commitments for Restart
- Restart Decision-Making
- Plan for Sustained Improvement
- Independent Assessment
- Closing Remarks November 15, 2012 1 2 Plant Status Industrial Safety Overview InjuryComparisonSummary
- Safety Performance 2011 2012
- Human Performance UntreatedInjuries: 23 18
- Fixing the Plant FirstAidInjuries: 22 5 OSHARecordable: 21 1 LostTime/Restricted: 1 0 2012dataJanuary1st toNovember14th 3 4 Enclosure 2
HumanPerformanceGoals Human Performance Overview DepartmentLevelPerformanceIssues WhatDoes"Excellence"LookLike?
HumanPerformanceSummary 140 134 2011 2012 120 Stationlevelissues 9 1 100 80 Departmentlevelissues 134 45 **Department Level Performance Goal 60 52 *2012 data January 1st to November 7th 40 25 45 12 20 6 6 ToDate*
2012dataJanuary1st toNovember14th 0 2011 **2012 **2013 **2014 **2015 **2016 IndustryBestisintheRangeof6to12peryear 5 6 Fixing the Plant Fixing the Plant Emergency Diesel 480 Volt AC Train A Generator No. 1 Bus Maintenance Voltage Regulator Complete Work Complete 7 8 Enclosure 2
ContinuedProgress OPPDCommitmentsforRestart
- Station Priorities 1. Identify causes and implement corrective actions for safety significant findings (Checklist 1.a through 1.d)
Safety 2. Assess safety culture and organizational effectiveness
Human Performance and implement improvement actions (Checklist 1.e and 1.f)
Insert Picture Fix the Plant 3. Assess and resolve flooding impact, evaluate systems,
Corrective Action and ensure plant is ready for restart (Checklist 2.a and 2.b)
Program 4. Assess and improve programs and processes that caused significant performance decline (Checklist 3.a
- Human Behavior through 3.f)
Continues to Improve 5. Implement the Integrated Performance Improvement Plan (Checklist 4)
- We are Fixing the Plant 6. Submit Fort Calhoun Station Restart Report
- Remaining Work is Known 9 10 CAL Commitment No. 1 Commitment 1 1.a. Flooding Issue Progress on Addressing Safety Findings
- Completed Scoping, Discovery and Analysis
- Completed Root Cause Analyses ScopingDiscoveryAnalysisImplementation
- Key Corrective Actions Completed 1.a. Flooding 100% 100% 100%
75% - Replacement of Certain Flood Barriers 1.b. Reactor Prot. - Inspection of All Conduit/Piping Seals Sys. Contactor 100% 100% 75% 75% - Improved Flood Procedures Failure 1.c. Electrical Bus 100% 100% 100% 75%
Modification & 85%
Maintenance Before After 1.d. Security Issue 100% 100% 90% 75%
11 12 Enclosure 2
CAL Commitment No. 1 CAL Commitment No. 2 1.a. Flooding Issue - Contd Commitment 2 Progress on Safety Culture and Organizational
- Completing Remaining Corrective Actions Effectiveness ScopingDiscoveryAnalysisImplementation
- Intake Cell Level Control Modification 1.e. Safety Culture 100% 100% 100% 93%
- Fire Barrier Certification for Flood Resistance 1.f. Organizational
- Phase A: Confirmed Static Pressure Effectiveness 100% 100% 100% 89%
Resistance
- Phase B: 30-Day Leakage Test Ongoing
- Restart Checklist Closure Package Ready for Inspection - November 30 13 14 CAL Commitment No. 2 CAL Commitment No. 2 1.e. Safety Culture 1.e. Safety Culture - Contd Improvement Actions
- Independent and Internal Assessments Identified Areas for Improvement
- Developed, Communicated and Aligned on Strategic
- Develop and Communicate Strategic Vision, Plan; Vision, Mission, and Values; and Performance Governance and Oversight - Complete Management and Accountability Process
- Enhance Leadership Behaviors - Ongoing
- Bi-Weekly Employee 2Cs Meetings
- Engage Workforce in Decisions Based on Vision -
- Daily Leaders and Weekly Staff Alignment Meetings Ongoing
- Differing Professional Opinion Process Established
- Improve Corrective Action Program - Ongoing
- Safety Conscious Work Environment Training for
- Encourage Questioning Attitude and Challenging Supervisors Complete and Ongoing for Employees -
of Decisions - Ongoing Complete in December
- Re-Assessment Completed in October
- Improve Accountability - Ongoing 15 16 Enclosure 2
CAL Commitment No. 2 CAL Commitment No. 2 1.e. Safety Culture - Contd 1.e. Safety Culture - Contd Safety Culture Monitoring Results
- Elements of Safety Culture Metric Safety Conscious Work Environment Index
- Safety Conscious Work Environment Index Improving
- Nuclear Safety Culture Principals Index - Management Takes Concerns Seriously
- Engaged Thinking Organization Index - Culture Conducive to Raising Concerns (INPO SOER 10-02) - Awareness and Willingness to Use ECP
- Employee Engagement Index - Comfortable Escalating Concerns
- INPO Organizational Culture Index Nuclear Safety Culture Principles Index Improving
- Metric Monitored Monthly - Input from Pulse - Supervisors Reinforcing use of Human Surveys Performance Tools
- Staff Encouraged to Bring Problems Forward
- Supervisors Reinforcing use of Operating Experience 17 18 CAL Commitment No. 2 CAL Commitment No. 3 1.e. Safety Culture - Contd Commitment 3 Safety Culture Monitoring Results Progress on Systems Ready for Restart
- Management Focus Areas ScopingDiscoveryAnalysisImplementation 2.a. Flood Recovery 93%
100% 100% 100% 91%
- Managing Distractions Restoration Actions
- Inter-Department Communications 100%
2.b.1. System Health 50%
100% 70% 10%
- Coordinating Issues Between Work Groups Reviews
- Employee Concerns Program Confidentiality 2.b.2. Reactor Safety 50%
Strategic Performance 100% 100% 100%
Area Review 0%
19 20 Enclosure 2
CAL Commitment No. 3 CAL Commitment No. 3 Commitment 3 2.a. Flood Recovery Restoration Actions Progress on Systems Ready for Restart - Contd
- Fort Calhoun Station Flooding Recovery Plan
- 453 Actions in Six Sections ScopingDiscoveryAnalysisImplementation
- Site Restoration 2.b.3. Flood Impact 100% 100% 95% 80%
- Plant Systems and Equipment on Soils & Structures
- Long Term Equipment Reliability 2.b.4. Containment 100% 100% 75% 10%
- Design and Licensing Basis Penetration Design
- Emergency Planning 2.b.5. Containment
- Security 100% 90% 75% 5%
Internal Structure - Flood Restoration Actions Part of the Integrated Design Performance Improvement Plan 21 22 CAL Commitment No. 3 CAL Commitment No. 3 2.a. Flood Recovery Restoration Actions 2.b.1 System Health Reviews
- Total Flood Recovery Plan
- 453 Actions
- Process Documented in a Station Procedure
- Physical Work Complete
- Evaluating Important Plant Systems
- 410 Actions
- Identify Issues that Could Affect System Health
- Closure Review Board Complete
- Enter Issues into Corrective Action Program
- 343 Actions
- Provide Confidence that Systems are Ready for
- NRC Inspection Plan Restart
- 196 Actions
- NRC Inspection Complete
- 67 Actions 23 24 Enclosure 2
CAL Commitment No. 3 CAL Commitment No. 3 2.b.3. Flood Impact on Soils & Structures 2.b.4 Containment Penetration Design Final Actions
- Local Expert Geotechnical Firms Analysis Final Fort Calhoun Staff Identified 614 Containment Report Issued on September 18, 2012 Penetrations that Could Degrade under Certain Potential Accident Conditions
- Issuance of Final Safety-Qualified Expert Firms Analysis Final Report Delayed
- Approximately 170 Unused Penetrations will be
- Conclusion - No Negative Effects on Safety-Related Capped Structures
- Approximately Ten Penetrations will be Replaced
- Options are Being Evaluated for Resolution of the
- Restart Checklist Closure Package Ready for Remaining Penetrations Inspection - December 25 26 CAL Commitment No. 3 CAL Commitment No. 4 2.b.5 Containment Internal Structure Design Commitment 4 Fort Calhoun Staff Identified Certain Structural Progress on Programs and Processes Elements Inside the Containment may not Meet Ready for Restart ScopingDiscoveryAnalysisImplementation Design Margins - Containment Shell not Affected 3.a. Corrective 100% 100% 100% 70%
Action Program
- Completed As-Built Verifications and Discovery 3.a.1. Identify, Analyze 50%
100% 100% 100%
nearly Complete & Correct Performance Deficiencies
- Developed Engineering Models for Analysis
- Analyzed Internal Structures using Current 3.b.1. Safety 100% 100% 75% 5%
Licensing Requirements Related Parts
- Evaluating Options for Resolution 3.b.2. Equipment 100% 90% 20%
Qualification 60%
27 28 Enclosure 2
CAL Commitment No. 4 CAL Commitment No. 4 Commitment 4 Commitment 4 Progress on Programs and Processes Progress on Programs and Processes Ready for Restart - Contd Ready for Restart - Contd ScopingDiscoveryAnalysisImplementation ScopingDiscoveryAnalysisImplementation 3.c.1. Vendor 100% 100% 95% 10% 3.e.1. Operability 100%
Modifications 100% 80% 15%
Determinations 3.c.2. 10CFR50.59 20%
100% 98% 75% 3.e.2. Degraded /
Screening & Safety 15%
Non-Conforming 100% 100% 80%
Evaluations Equipment 55%
3.d.1. Vendor 100% 100% 95%
Manuals 3.f. Quality 100% 100% 100% 83%
Assurance 3.d.2. Equipment 100% 100% 95% 5%
Service Life 29 30 CAL Commitment No. 4 CAL Commitment No. 4 3.a. Corrective Action Program (CAP) 3.a. Corrective Action Program (CAP)
- Corrective Action Program Metric Elements
- Fort Calhoun Staff has been Implementing Improved - Condition Report Generation CAP Process for Six Months - Engagement Ratio
- Good Catches
- Process Implementation Improvement and - Self-Identification Rate Effectiveness Observed
- Repeat Events
- Review Rejection Rate
- Expected Behaviors and Culture Being Reinforced
- Age of Reviews and Actions
- Overdue Reviews and Actions
- Number of Open Condition Reports 31 32 Enclosure 2
CAL Commitment No. 5 CAL Commitment No. 5 Commitment 5 Restart Decision-Making Criteria Integrated Performance Improvement Plan (IPIP)
- Restart Checklist Items Resolved
- Confirmatory Action Letter Commitments Addressed
- IPIP Revision 4 Docketed November 1
- Operational Readiness Assessment Completed
- Systems, Programs and Departments Determined to be Ready for Restart
- Addresses Restart Decision-Making Process and Criteria
- Independent Assessments Completed
- Nuclear Oversight Department
- Corporate Governance and Oversight Committee
- Describes Plan for Sustained - Safety Audit and Review Committee Improvement
- Operating Services Agreement is the Foundation for Achieving and Sustaining Excellence
- Blended OPPD/Exelon Leadership Team Functioning Effectively IndependentAssessments
- Integration Team of Exelon Experts Providing Site Support and Transition Planning in 22 Functional Areas
- Goal - Implement the Exelon Nuclear Management Model and Full Integration into the Exelon Fleet 35 36 Enclosure 2
OPPDs Commitment Tonight We Updated You on
- Plant Status - Fixing the Plant
- Progress on Commitments for Restart
- Restart Decision-Making
- Plan for Sustained Improvement
- Independent Assessments 37 Enclosure 2